BYRON 2010-0042, Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 2, (B2R15)

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Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 2, (B2R15)
ML102180221
Person / Time
Site: Byron Constellation icon.png
Issue date: 08/03/2010
From: Enright D
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
1.10.0101, BYRON 2010-0042
Download: ML102180221 (221)
v • d • e


Text

Exelon Generation Company, LLC www.exeloncorp.com Exelon.

Byron Station NUdeaT 445o North German Church Road Byron, IL61010-9794 August 3, 2010 LTR: BYRON 2010-0042 FILE: 1.10.0101 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 2 Facility Operating License No. NPF-66 NRC Docket No. STN50-455

SUBJECT:

Byron Station Unit 2 90-Day Inservice Inspection Report for Interval 3, Period 2, (B2R15)

The subject 90-Day Inservice inspection Report for the Byron Station Unit 2, Refueling Outage Fifteen (B2R15) is being submitted pursuant to the requirements of Article IWA-6000, "Records and Reports" of Section XI, "Rules for Inservice inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code 200i Edition through the 2003 Addenda. The report covers the inservice inspections conducted prior to and during the Unit 2 Spring 2010 refueling outage.

If there are any questions regarding this matter, please contact Dave Gudger, Regulatory Assurance Manager, at (815)-406-2800.

Respectfully, Daniel J. Enright Site Vice President Byron Generating Station DJE/RGM,/TLH/cy

Attachment:

B2R15 Inservice Inspection Summary Report - Spring 2010 outage 404-7 1kJ(v4

BYRON Exelon..

UNIT 2 Nuclear B2R15 Spring 2010 Outage INSERVICE INSPECTION

SUMMARY

REPORT For Inspection Activities from October 24, 2008 to May 8, 2010 Commercial Service Date August 21, 1987 Document Completion Date July 29, 2010 Exelon Generation Company (EGC, LLC) 4300 Winfield Rd Warrenville, IL 60555 Byron Nuclear Power Station 4450 North German Church Rd.

Byron, IL 61010.

BYRON UNIT 2 Exelon.

Nuclear B2R15 INSERVICE INSPECTION

SUMMARY

REPORT SECTION SECTION DESCRIPTION PAGES ICover Page 1 Iii ITable of Contents 1 1 1.0 Report Introduction 6 ISI - Weld / Component Listing 18 ISI - Bolts, Pumps, and Valves Listing 1 Examination PSI - Weld / Component Listing 1 2.0 Summary PSI - Bolts, Pumps, and Valves Listing 2 Tables ISI - Pressure Tests 12 ISI - Component Supports 9 ISI - Snubbers 11 1 3.0 IStatus of Examination Completion for the Program Plan 7 1 4.0 IForm NIS-I: Preservice and Inservice Examinations 5=3 1 5.0 lForm NIS-2: Repairs/ Modifications 49 I TOTAL PAGES IN REPORTI 171

SECTION 1.0 BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.

1.0 INTRODUCTION

Inservice inspections of American Society of Mechanical Engineers (ASME) Class 1, 2, 3, CC, and MC components were conducted at Byron Station Unit 2 from October 24, 2008 through May 8, 2010. The majority of these inspections were performed during the fifteenth refueling outage (B2R15) from April 19 through May 8, 2010.

B2R1 5 is the first outage of the Second Period in the Third Inspection Interval.

The examinations were performed in compliance with the rules and regulations of ASME Section Xl 2001 Edition, through the 2003 Addenda, pursuant to the requirements of 10 CFR 50.55a.

See 1.7.0 of the introduction for a listing of referenced documents.

This summary report meets the requirements of ASME Code, IWA-6000 for the inspection of Class 1 and 2 components and piping. Class CC and MC components in the Containment Inservice Inspection (CISI) program are included when examination results require reporting as specified in 10 CFR 50.55a.

The Nondestructive Examination (NDE) Inservice Inspection (ISI) Program Plan for Class 1, 2, 3, CC, and MC components was developed in accordance with the requirements and intent of Section Xl Subsections IWA, IWB, IWC, IWD, IWE, IWF and IWL, 2001 Edition, through the 2003 Addenda.

In addition to the ASME Section Xl requirements of examination, certain Nuclear Regulatory Commission (NRC) augmented ISI inspections and industry initiatives (NEI-03-08) were required. The Byron Station Unit 2 augmented ISI examination requirements include:

6 Class 1 pressure boundary examinations for leakage at nominal operating pressure, in accordance with NRC Generic Letter 88-05;

  • Class 1 Alloy 600 weld examinations in accordance with MRP-139, N-722, and N-729-1; 6 Class 2 and 3 pressure boundary examinations for leakage at nominal operating pressure, in accordance with NUREG 0737.
  • Class 1 examinations of non-isolable Reactor Coolant System branch lines for Thermal Fatigue in accordance with MRP-146; Specific requests for relief were developed and submitted for the NRC's review when the code and/or augmented requirement(s) were deemed to be impractical, results in excessive hardship, or an alternative examination method is determined as more suitable for the particular component.

Section 1.0 Page 1 of 6

BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.1 Identification of Examination Requirements The Section 7.0 of the ISI Program Plan contains the examination program tables.

These tables are consistent with the tables found in Subsections IWB, IWC, IWD, IWE, IWF, and IWL-2500 of the ASME Code. The examination tables include the corresponding code category, item number, and component/weld selection in conformance with examination requirements and intent of Section Xl.

For Class 1, 2, and certain non-class piping components, the requirements of Risk Informed Inservice Inspection (RI-ISI) are followed using EPRI TRI 12657 and Table 1 of ASME Code Case N-578-1.

1.1.2 Identification of Exempted Components ASME Class 1, 2, and 3 components, or parts of components, that are not included in the examination tables and that are exempt from examination, as specified in Section Xl Paragraphs IWB, IWC, and IWD-1200, and Tables IWB-2500-1, IWC-2500-1, and IWD-2500-1, are identified in the NDE Program Plan in conjunction with technical justification(s) for exempting the component/system.

Class 1 or 2 piping welds exempted by IWB and IWC-1200 are not included in the RI-ISI program. Previous selection and examination exemptions identified in Tables IWB and IWC-2500-1 for Examination Categories B-F, B-J, C-F-i, and C-F-2, are not allowed under the requirements of the RI-ISI program. With the adoption of RI-ISI, welds evaluated as Risk Category 6 or 7 are not subject to examination.

1.1.3 Implementation of the ISI Program Exelon Nuclear, or its designee, examined ASME components utilizing the following methods: MT, PT, UT, VT-1, VT-2, and VT-3. The components examined comply with the ISI Program Schedule, Byron Station Technical Specifications, and/or comply with the ASME Section Xl Repair/Replacement Program.

Personnel certified in nondestructive examination are qualified in accordance with ANSI/ASNT CP-1 89, 1995 Edition and ASME Section Xl, 2001 Edition through 2003 Addenda including December 2003 Erratum.

All personnel performing ASME Section Xl ultrasonic examinations are qualified to the requirements of ASME Section Xl Appendix VII.

The NDE procedures were developed and qualified in-conformance with ASME Section V and XI as applicable.

All ISI NDE, including evaluation of flaw indications, were performed in accordance with the requirements stipulated under Section XI IWA-2200. For components incorporated into the RI-ISI program, the guidance for the examination volume for a given degradation mechanism is provided by the EPRI Topical Report while the guidance for the examination method is provided by Code Case N-578-1.

Section 1.0 Page 2 of 6

BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.1.4 Siginificant Activities During B2R15 During the refueling outage, the Alloy 600 welds were examined for PWSCC per the requirements specified in N-722:

" All reactor vessel bottom-mounted instrument penetrations were visually examined for leakage Item 115.80 weldments.

" All reactor vessel hot leg safe-end welds were visually examined for leakage for Item B15.90 weldments.

" One Alloy 600 reactor vessel cold leg safe-end weld was visually examined for leakage for Item B15.95 weldments.

" The steam generator primary channel head drains were visually examined for leakage for Item B15.120 weldments.

The reactor vessel head exterior surface was visually examined for evidence of leakage per the requirements specified in N-729-1 Note (4) for Item B4.1 0 components. One repaired reactor head penetration was examined with surface and volumetric methods per Item B4.20 and the approved relief request 13R-16.

All weld overlays on the pressurizer safe-end welds were volumetrically examined.

This examination complies with the requirements specified in MRP-139 for Category F welds and ASME Appendix Q Paragraph Q-4300(a). Use of Appendix Q was addressed in relief request 13R-08.

1.1.5 ASME Section Xl Code Cases N-566-2 is incorporated into the current Byron Station ISI Program and was utilized during this fuel cycle.

The implementation of the risk-informed program as described in relief request 13R-02 utilized N-578-1 during this Inspection Interval.

For Repair/Replacement activities, code cases are identified on the applicable Form NIS-2.

1.1.6 Witness and Verification of Examination The inservice inspections were witnessed and/or verified by Authorized Nuclear Inservice Inspectors (ANII) associated with Hartford Steam Boiler CT of Hartford, Connecticut, Chicago Branch, at 2443 Warrenville Rd., Suite 500, Lisle, Illinois 60532.

1.1.7 Corrective Measures A surface examination revealed two indications located in the fusion zone between two weld beads of an attachment weld on the 12" SI pipe to the flued head Penetration P-66 closure. The weld is identified in the Inservice Inspection Program as 2SI04B-1 2/C02 and was examined as Observation 15-203 in the outage. The Section 1.0 Page 3 of 6

BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT weld was selected under ASME Section Xl Class 2 Examination Category C-C; Item C3.20. The indications were described in Issue Report 01057786 and OE 31183.

The indications were near the weld toe on the flued head side of the fillet weld. The indications followed the interface between the beads while being removed and were thus classified as lack of fusion. The areas of the indications were blended and the indications were completely removed.

Additional examinations were performed on other attachment welds of similar materials and service per the requirements of ASME XI IWC-2430. Welds 2RH01 BA-1 2/C03 and 2SI05BA-8/C02 were examined as Observations15-223 and 15-221 respectively. The additional examinations were acceptable and no other code related actions are required.

1.2.0 EXAMINATION SUMMARIES The following section lists the summaries of examinations performed during the refueling cycle. Refer to Section 2.0 for each summary table for information or for specific tests and examinations conducted during this term.

Welds & Components Summaries Inservice Inspection - Weld / Component Listing Inservice Inspection - Bolts, Pumps, and Valves Listing Preservice Inspection - Weld / Component Listing Preservice Inspection - Bolts, Pumps, and Valves Listing

  • System Pressure Test Summaries
  • Component Support Examination Summary
  • Component Snubber Test Summary 1.3.0 UNIT 2 EXAMINATION COMPLETION STATUS A summary table of the examination status of Class 1 and 2 components is contained in Section 3.0.

1.4.0 FORM NIS-1 DATA SHEETS ASME Form NIS-1 were filed during the cycle for Unit 2. See Section 4.0 for the reports.

1.5.0 FORM NIS-2 DATA SHEETS ASME Form NIS-2 were filed during the cycle for Unit 2. See Section 5.0 for the reports.

Section 1.0 Page 4 of 6

BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT 1.6.0 CONTAINMENT ISI PROGRAM No reportable conditions were identified for Class CC and Class MC components during this fuel cycle.

1.7.0 REFERENCED DOCUMENTS 1.7.1 Code of Federal Regulations, Title 10 Energv Part 50: Domestic Licensing of Productionand Utilization Facilities.

50.55a: Codes and Standards.

1.7.2 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section V: Nondestructive Examination, 2001 Edition, through 2003 Addenda.

Section XI: Rules for Inservice Inspection of Nuclear Power PlantComponents, 2001 Edition, through 2003 Addenda.

IWA-2200: Examination Methods.

IWA-6000: Records and Reports.

IWB, IWC: and IWD-1 200, Components Exempt from Examination.

IWB, IWC: and IWD-2500, Examination and Pressure Test Requirements.

IWC-2430: Additional Examinations.

IWC-3512: Standards for Examination Category C-C, Welded Attachments for Vessels, Piping, Pumps, and Valves.

Appendix I1: Owner's Reports for Inservice Inspections.

Form NIS-1: Owners Report for Inservice Inspections.

Form NIS-2: Owners Report for Repairs or Replacements.

Appendix VII: Qualification of Nondestructive Examination Personnel for Ultrasonic Examination.

Code Case N-504-3: Alternative Rules for Repairof Classes 1, 2, and 3 Austenitic Stainless Steel Piping.

Code Case N-566-2: Corrective Action for Leakage Identified at Bolted Connections.

Code Case N-578-1: Risk-Informed Requirements for Class 1, 2, or 3 Piping, Method B.

Code Case N-722: Additional Examinationsfor PWR Pressure Retaining Welds in Class 1 Components FabricatedWith Alloy 600/82/182 Materials.

Code Case N-729-1: Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-RetainingPartial-Penetration Welds.

Section 1.0 Page 5 of

BYRON STATION UNIT 2 REFUELING OUTAGE 15 INSERVICE INSPECTION REPORT Nonmandatory Appendix Q: Weld Overlay Repairof Class 1, 2, and 3 Austenitic Stainless Steel Piping Weldments (2004 Edition, through 2005 Addenda). Appendix Q was required for the installation of the weld overlays using Code Case N-504-3.

Section Q-4300: Inservice Inspection.

1.7.3 American National Standards Institute / American Society for Nondestructive Testing ANSI/ASNT CP-1 89:1995 Edition, Standardfor Qualificationand Certificationof Nondestructive Testing Personnel.

1.7.4 Miscellaneous NRC Documents Generic Letter 88-05: Boric Acid Corrosionof Carbon Steel Reactor Pressure Boundary Components in PWR Plants.

NUREG 0737: Clarificationof TMI Action Plan Requirements.

Regulatory Guide RG 1.14: Reactor Coolant Pump Flywheel Integrity.

1.7.5 Electric Power Research Institute Material Reliability Program: PrimarySystem Piping Butt Weld Inspection and Evaluation Guideline (MRP-1 39) Revision 1, December 2008.

Material Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines (MRP-1 46), June 2005.

Topical Report TR1 12657: Revision B-A, Revised Risk-Informed Inservice Inspection Procedure,December 1999.

1.7.6 Nuclear Energy Institute NEI 03-08: Guideline for the Management of Materials Issues.

1.7.7 Byron Station Documents Relief Request 13R-02: Alternate Risk-Informed Selection and Examination Criteria for Category B-F, B-J, C-F-1, and C-F-2 PressureRetaining Piping Welds.

Relief Request 13R-08: Alternative Requirements of Structural Weld Overlays (SWOLs) of the PressurizerSurge, Spray, Safety and Relief Nozzles, Dissimilar Welds including the SWOLs of the Safe-End to Pipe, Reducer and Elbow Welds on PressurizerSurge, Spray, Safety and Relief Nozzles.

Relief Request 13R-1 6: Alternate Examination Frequency underASME Code Case N-729-1 for Reactor Vessel Head Penetration Welds.

Issue Report 01057786: Recordable Indications Discovered During ISI Examination.

1.7.8 Institute of Nuclear Power Operations 0E31183: Unacceptable Surface Indicationson a Safety Injection Flued Head Penetration Weld.

Section 1.0 Page 6 of 6

SECTION 2.0 7/29/2010 Exelin.,

Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Chemical & Volume Control System (CV)

Section Xl TComponent ID Linee:Nuber Relief Technical . code Acual Resul'ts Cat' Description Requests Notes. Coverage .d Exam Comments R-A R1.11 2CVA3B-21W-70 2CVA3B-2 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-005 R-A R1.11 2CVA3B-2/W-71 2CVA3B-2 13R-02 B9.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02.

OBS15-006 R-A R1.11 2CVA3B-2/W-72 2CVA3B-2 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-007 R-A RI.11 2CVA3B-2/W-73 2CVA3B-2 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-008 R-A R1.1 1 2CVA3B-2/W-80 2CVA3B-2 13R-02 B9.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-009 R-A R1.11 2CVA3B-2/W-81 2CVA3B-2 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-010 R-A R1.11 2CVA5AA-2/W-06 2CVA5AA-2 13R-02 B9.40 VT-2 NRI Pipe - Elbow 13T-01, 13T-02 OBS15-011 R-A R1.11 2CVA5AA-2/W-07 2CVA5AA-2 13R-02 B9.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-012 R-A R1.11 2CVA6AA-2/W-04 2CVA6AA-2 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-013 R-A R1.1 1 2CVA6AA-2/W-05 2CVA6AA-2 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-014 R-A R1.11 2CVA7AA-2/W-06 2CVA7AA-2 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-050 1

7/29/2010 Exel mn..

Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Chemical & Volume Control System (CV)

Section XI, Compoonent ID LineNumber Relief 'Technical Code r tua[' ]-Results Cat. Description Requests Notes' Coverage7 Exam'.

Comments' R-A R1.11 2CVA7AA-2/W-07 2CVA7AA-2 13R-02 B9.40 VT-2 NRI Elbow - Pipe 13t-01 13T-02 OBS15-051 R-A RI.11 2CVA7AA-2/W-08 2CVA7AA-2 13R-02 B9.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-052 2

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Feedwater System (FW)

Section Xl 0Component ID , Line Number, Relief. >Technical Code. 1,.* Actuai Results Ca. Description -.Reiet k!ote s. Cvrg Exam Comments .

R-A R1.11 2FW03DA-16/CO1 2FW03DA-16 13R-02 C5.51 100 UT NRI R1.18 Valve-Pipe 13T-01 13T-02 OBS15-102 R-A R1.11 2FW03DA-16/C02 2FW03DA-16 13R-02 C5.51 100 UT GEOM R1.18 Pipe - Penetration 13T-01 13T-02 OBS15-103 ID Geometry 3600 Intermittent.

R-A R1.11 2FW81BA-6/C07 2FW81BA-6 13R-02 C5.51 99 UT NRI R1.18 Pipe-Tee 13T-01 13T-02 OBS15-104 Coverage reduced due to adjacent branch connection on tee side.

R-A R1.1l 2FW87CA-6/CO1 2FW87CA-6 13R-02 C5.51 99 UT NRI R1.18 Reducer-Tee 13T-01 13T-02 OBS15-105 Coverage reduced due to adjacent branch connection on tee side.

R-A R1.11 2FW87CA-6/C02 2FW87CA-6 13R-02 C5.51 98 UT GEOM R1.18 Tee-Pipe 13T-01 13T-02 OBS15-106 ID Geometry 3600 Intermittent. Coverage reduced due to adjacent branch connection on tee side.

R-A R1.11 2FW87CA-6/C03 2FW87CA-6 13R-02 C5.51 100 UT GEOM R1.18 Pipe - Penetration 13T-01 13T-02 OBS15-107 ID Geometry 3600 Intermittent.

C-C C3.20 2FW87CA-6/C04 2FW87CA-6 100 MT NRI Closure Plate 2PC-100 OBS15-108 3

7/29/2010 ExeI4 n,n Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Pressurizer (PZR)

ýSection XI Component ID Line Number . :rRie -Technica[* Cd cua eut Cat. Description j,,,'Requests,,-,, Notes., Coverage Exam Comments B-B B2.11 2RY-01-S/PC-05 2RY-01-S .96 UT NRI Shell - Upper Head OBS15-128 Scanning obstructed by 4 welded insulation pads.

B-B B2.12 2RY-01-S/PL-04 2RY-01-S 100 UT NRI Upper Longitudinal Weld OBS15-129 B-D B3.110 2RY-01-S/PN-02 2RY-01-S 13R-12 62 UT NRI Spray Nozzle OBS15-131 Limited examination due to nozzle to vessel configuration.

B-D 83.120 2RY-01-S/PN-02-NIR 2RY-01-S UT NRI Spray Nozzle Inner Radius OBS15-133 B-D B3.110 2RY-01-S/PN-03 2RY-01-S 13R-12 66 UT NRI PORV Nozzle OBS15-136 Limited examination due to nozzle to vessel configuration.

B-D B3.120 2RY-01-S/PN-03-NIR 2RY-01-S UT NRI Relief Nozzle Inner Radius OBS15-136 B-D 83.120 2RY-01-S/PN-05-NIR 2RY-01-S UT NRI Relief Nozzle Inner Radius OBS15-139 B-D B3.110 2RY-01-S/PN-06 2RY-01-S 13R-12 66 UT NRI Relief Nozzle OBS15-140 Limited examination due to nozzle to vessel configuration.

B-D B3.120 2RY-01-S/PN-06-NIR 2RY-01-S UT NRI Relief Nozzle Inner Radius OBS15-142 4

7/29/2010ExIn

~Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report Weld Component Outage Summary SYSTEM: Reactor Coolant System (RC)

~Setin ChionntlDbf~r I L neNib6iýbe,ýt Relief" ~T4echmic'all '+~eý':' ,. ., 46t4aLýl, Resu tsi ppequestion Notes , oveage Exam

ýComments' R-A R1.20 2RC01AA-29/J06 2RC01AA-29 13R-02. B9.40 VT-2 NRI SOL - Thermowell 13T-01 13T-02 OBS15-015 R-A R1.15 2RC-01-R/RPVS-A F1 2RC-01-R 13R-02 B5.10 BMV NRI B15.90 RPV Nozzle Safe-End HL Loop D 13T-01 13T-02 OBS15-185 Hot Leg Bare Metal exam per N-722 requirements. See WO#01 182316.

R-A R1.15 2RC-01-R/RPVS-D F1 2RC-01-R 13R-02 B5.10 BMV NRI B15.90 RPV Nozzle Safe-End HL Loop C 13T-01 13T-02 OBS15-186 Hot Leg Bare Metal exam per N-722 requirements. See WO#01 182316.

R-A R1.15 2RC-01-R/RPVS-E F1 2RC-01-R 13R-02 B5.10 BMV NRI B15.90 RPV Nozzle Safe-End HL Loop B 13T-01 13T-02 OBS15-187 Hot Leg Bare Metal exam per N-722 requirements. See WO#01 182316.

R-A R1.15 2RC-01-R/RPVS-F F1 2RC-01-R 13R-02 B5.10 VT-2 NRI B15.95 RPV Nozzle Safe-End CL Loop B 13T-01 13T-02 OBS15-225 Bare Metal exam per N-722 requirements. See WO#01300973.

R-A R1.15 2RC-01-R/RPVS-H F1 2RC-01-R 13R-02 85.10 BMV NRI B15.90 RPV Nozzle Safe-End HL Loop A - 13T-01 13T-02 OBS15-188 Hot Leg Bare Metal exam per N-722 requirements. See WO#01 182316.

R-A R1.20 2RC03AA-27.5/JO2A 2RC03AA-27.5 13R-02 B9.40 VT-2 NRI SOL - Thermowell 13T-01 13T-02 OBS15-016 R-A R1.20 2RC03AA-27.5/J04 2RC03AA-27.5 13R-02 B9.40 VT-2 NRI SOL - Thermowell 13T-01 13T-02 OBS15-017 R-A R1.20 2RC13AA-2/W-01 2RC13AA-2 13R-02 B9.40 VT-2 NRI SOL - Pipe 13T-01 13T-02 OBS15-026 R-A R1.20 2RC13AA-2/W-02 2RC13AA-2 13R-02 B9.40 VT-2 NRI Pipe - Tee 13T-01 13T-02 OBS15-027 5

7/29/2010 Exelen.

Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)

Section XI Component iD) Line Number,,-. Relief -. :Technicai Code Actual Results,]

rCat. Descrption Requests'- Notes 0Coveage Exam Comments"-

R-A R1.20 2RC13AA-2/W-03 2RC13AA-2 13R B9.40 VT-2 NRI Tee - Reducer 13T-01 13T-02 OBS15-028 R-A R1.20 2RC13AA-2/W-04 2RC13AA-2 13R-02 B9.40 VT-2 NRI Tee - Pipe 13T-01 13T-02 OBS15-029 R-A R1.20 2RC13AA-2/W-05 2RC13AA-2 13R-02 B9.40 VT-2 NRI Pipe - Valve 13T-01 13T-02 OBS15-030 R-A R1.20 2RC13AB-2/W-01 2RC13AB-2 13R-02 B9.40 VT-2 NRI SOL - Pipe 13T-01 13T-02 OBS15-031 R-A R1.20 2RC13AC-2/W-01 2RC13AC-2 13R-02 B9.40 VT-2 NRI SOL - Pipe 13T-01 13T-02 OBS15-032 R-A R1.20 2RC13AD-2/W-01 2RC13AD-2 13R-02 B9.40 VT-2 NRI SOL - Pipe 13T-01 13T-02 OBS15-033 R-A R1.11 2RC14AA-2/W-01 2RC14AA-2 13R-02 89.40 VT-2 NRI SOL - Pipe 13T-01 13T-02 OBS15-036 R-A R1.11 2RC14AA-21W-01A 2RC14AA-2 13R-02 89.40 VT-2 NRI Pipe - Tee 13T-01 13T-02 OBS15-037 R-A R1.11 2RC14AA-2/W-01B 2RC14AA-2 13R-02 89.40 VT-2 NRI Tee - Reducer 13T-01 13T-02 OBS15-038 R-A R1.11 2RC14AA-2/W-01C 2RC14AA-2 13R-02 B9.40 VT-2 NRI Tee - Pipe 13T-01 13T-02 OBS15-039 R-A R1.11 2RC14AA-2/W-02 2RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-040 6

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)

,Secton*XI Cohiponent, D Line Number*,, , -," Relief -,Technicai Code I 'Actual , Results actKK  :~euss'.~o~~ Coverage ,Exam ~

IComments ~ ...- 4*.. . . ** " .. ... "

R-A R1.11 2RC14AA-2/W-03 2RC14AA-2 13R-02 B9.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-041 R-A R1.11 2RC14AA-2/W-04 2RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-042 R-A R1.11 2RC14AA-2/W-05 2RC14AA-2 13R-02 B9.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-043 R-A R1.11 2RC14AA-2/W-06 2RC14AA-2 13R-02 B9.40 VT-2 NRI Pipe - Valve 13T-01 13T-02 OBS15-044 R-A R1.11 2RC14AA-2/W-07 2RC14AA-2 13R-02 B9.40 VT-2 NRI Valve - Pipe 13T-01 13T-02 OBS15-045 R-A R1.11 2RC14AA-2/W-08 2RC14AA-2 13R-02 89.40 VT-2 NRI Pipe - Tee 13T-01 13T-02 OBS15-046 R-A R1.11 2RC14AA-2/W-09 2RC14AA-2 13R-02 89.40 VT-2 NRI Tee - Reducer 13T-01 13T-02 OBS15-047 R-A R1.11 2RC14AA-2/W-10 2RC14AA-2 13R-02 89.40 VT-2 NRI Tee - Pipe 13T-01 13T-02 OBS15-048 R-A R1.11 2RC14AA-2/W-11 2RC14AA-2 13R-02 89.40 VT-2 NRI Pipe - Valve 13T-01 13T-02 OBS15-049 R-A R1.11 2RC16AA-2/W-03 2RC16AA-2 13R-02 B9.40 VT-2 NRI Valve - Pipe 13T-01 13T-02 OBS15-053 R-A R1.11 2RC16AA-2/W-04 2RC16AA-2 13R-02 89.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-054 7

7/29/2010Ex I n Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)

Section XI Component ID .. Line Number, : Relief F- 'Technicai Code - - Actual Results

' Cat. Description "- Re'qesti ' Notes Coverage Exam Comments-R-A R1.11 2RC16AA-2/W-05 2RC16AA-2 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-055 R-A R1.11 2RC16AA-2/W-06 2RC16AA-2 13R-02 B9.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-056 R-A R1.11 2RC16AA-2/W-07 2RC16AA-2 13R-02 B9.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-057 R-A R1.11 2RC16AB-2/W-04 2RC16AB-2 13R-02 B9.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-058 R-A R1.11 2RC16AB-2/W-05 2RC16AB-2 13R-02 89.40 VT-2 NRI S"Elbow - Pipe 13T-01 13T-02 OBS15-059 R-A R1.20 2RC16AC-2/W-08 2RC16AC-2 13R-02 B9.40 VT-2 NRI Pipe - SOL 13T-01 13T-02 OBS15-024 R-A R1.20 2RC16AD-2/W-01 2RC16AD-2 13R-02 89.40 VT-2 NRI Valve - Pipe 13T-01 13T-02 OBS15-025 R-A R1.20 2RC22AA-1.5/W-01 2RC22AA-1.5 13R-02 B9.40 VT-2 NRI SOL - Pipe 13T-01 13T-02 OBS15-020 R-A R1.20 2RC22AA-1.5/W-05 2RC22AA-1.5 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-021 R-A R1,20 2RC22AC-1.5/W-01 2RC22AC-1.5 13R-02 89.40 VT-2 NRI SOL - Pipe 13T-01 13T-02 OBS15-022 R-A R1.20 2RC22AC-1.5/W-06 2RC22AC-1.5 13R-02 B9.40 VT-2 NRI Pipe - Tee 13T-01 13T-02 OBS15-023 8

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)

Seciion XI. component ID Line Number. .," Relief ,.; Technicai Code ActuaI:Results

'Cat. Description Reluests . oiýýt Exam Ex'COverage Comments R-A R1.20 2RC22AD-1.5/W-01 2RC22AD-1.5 13R-02 B9.40 VT-2 NRI SOLL- Pipe 13T-01 13T-02 OBS15-018 R-A R1.20 2RC22AD-1.5/W-08 2RC22AD-1.5 13R-02 B9.40 VT-2 NRI Pipe - Tee 13T-01 13T-02 OBS15-019 R-A R1.20 2RC26A-2/W-01 2RC26A-2 13R-02 B9.40 VT-2 NRI SOL - Pipe 13T-01 13T-02 OBS15-034 R-A R1.20 2RC26A-2/W-02 2RC26A-2 13R-02 B9.40 VT-2 NRI Pipe - Valve 13T-01 13T-02 OBS15-035 N/A N/A 2RC28A-3/Zone 1 2RC28A-3 91 UT NRI Elbow - SOL VT-2 NRI OBS15-212 Volumetric and bare metal visual per MRP-146.

Scanning obstructed due to elbow to branch configuration.

R-A R1.11 2RC30AA-1.5/W-01 2RC30AA-1.5 13R-02 B9.40 VT-2 NRI Valve - Reducer 13T-01 13T-02 OBS15-079 R-A R1.20 2RC35AA-6/J02 2RC35AA-6 13R-02 B9.11 100 UT NRI Pipe - Elbow 13T-01 13T-02 OBS15-199 ID Geometry 360' Intermittent seen below recording levels.

R-A R1.20 2RC35AA-6/J03 2RC35AA-6 13R-02 139.11 100 UT NRI Elbow - Pipe 13T-01 13T-02 OBS15-200 ID Geometry 3600 Intermittent seen below recording levels.

R-A R1.11 2RC35AA-6/J04 2RC35AA-6 13R-02 B9.11 100 UT NRI Pipe - Elbow 13T-01 13T-02 OBS15-201 ID Geometry 3600 Intermittent seen below recording levels.

R-A R1.11 2RC35AA-6/J05 2RC35AA-6 13R-02 B9.11 100 UT NRI Elbow - Pipe 13T-01 13T-02 OBS15-202 ID Geometry 3600 Intermittent seen below recording levels.

9

7/29/2010 Exelon,n Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RC)

Section Xl Component iD,, Line Nume Relief Tehia oe Actual, Results

'Cat Requests , otes* Coverage Exam Cdmmbnts' N/A N/A 2RC37A-3/Zone 2 2RC37A-3 91 UT NRI Elbow - SOL VT-2 NRI OBS15-213 Volumetric and bare metal visual per MRP-146.

Scanning obstructed due to elbow to branch configuration.

10

7/29/2010 Exeloin.

Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Residual Heat Removal System (RH)

Section Xl component ID Line Numbeer. Re ieef Technica[ Code-. j Actual ]Results Cat. Description

.. .. , . , t" Requests, . Notes CoVerage Exam, Commentsý C-C C3.20 2RH01BA-12/C03 2RH01BA-12 100 PT NRI Closure Plate.2PC-68 OBS15-223 WO# 01330140. Additional examination for OBS15-203.

C-C C3.20 2RH02AA-8/C47 2RH02AA-8 100 PT IND Closure Plate 2AB-37 OBS15-181 1/16" Rounded Indication on penetration plate 0.25" from weld toe. Acceptable per procedure. Ref. RIR B2R15-PT-010.

11

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISl Outage Report Weld / Component Outage Summary SYSTEM: Reactor Pressure Vessel (RPV)

Sýection XiL component'iD 1ine.Number, , iReief I*, ehnica  ;'l Cde Actal ResultS.

Cat.

S pesriptio'n Requests ',,Notes Coerage Exam Comments',

N/A B15.80 2RC-01-R/RPV BMI 2RC-01-R 100 VE NRI RPV Bottom Mounted Instruments OBS15-217 Detailed examination of head surface and annular area of the penetrations. Ref. WO 01019896 B-E B4.20 2RC-01-R/RPV HEAD 2RC-01-R 13R-16 100 UT. RI PEN RPV Head Penetrations J-Weld 13R-18 100 PT NRI OBS15-218 Examination per N-729-1 requirements. Penetration 68 only. See WO#01 186189. Indication classified as fabrication flaw from repair weldingin B2R13. No change in flaw seen in this examination.

B-E B4.10 2RC-01-R/RPV HEAD 2RC-01-R 100 BMV NRI SURF RPV Head Penetrations OBS15-219 Detailed examination of head surface and annular area of the penetrations. Ref. WO 01181363 B-N-1 B13.10 2RC-01-R/RPV 2RC-01-R VT-3 NRI INTERIOR RPV Interior Surfaces OBS15-220 Debris found reference IR 01061204. All other conditions acceptable.

12

7/29/2010 Exel mn.

Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RY)

Component ID. Line Nuimber,- Relief ,. Technical -- Code ,,Acualct Results Section Xl ...

Cat. IDescription Requests Notes coverageExam Comments .

R-A R1.11 2RY01B-6/J28 2RY01B-6 13R-02 B9.11 100 UT NRI Elbow - Pipe 13T-01 13T-02 OBS15-156 ID Geometry 3600 Intermittent seen below recording levels.

R-A R1.11 2RY01B-6/J29 2RY01B-6 13R-02 B9.11 100 UT NRI Pipe - Elbow 13T-01 13T-02 OBS15-157 ID Geometry 360' Intermittent seen below recording levels.

R-A R1.11 2RY01B-6/J30 2RY01B-6 13R-02 89.11 100 UT NRI Elbow - Reducer 13T-01 13T-02 OBS15-158 ID Geometry 360' Intermittent seen below recording levels.

N/A N/A 2RY01C-4/J01S 2RY01C-4 13R-08 100 UT NRI Reducer - Spray Nozzle Overlay OBS15-159 Reexamination per Appendix Q requirements.

N/A N/A 2RY-01-S/PN-01-F1S 2RY-01-S 13R-08 100 UT NRI Surge Nozzle-Safe End Overlay OBS15-130 Reexamination per Appendix Q and MRP-139 Category F requirements.

N/A N/A 2RY-01-S/PN-02-F2S 2RY-01-S 13R-08 100 UT NRI Spray Nozzle-Safe End Overlay OBS15-132 Reexamination per Appendix Q and MRP-139 Category F requirements.

N/A N/A 2RY-01 -S/PN-03-F3S 2RY-01-S 13R-08 100 UT NRI PORV Nozzle-Safe End Overlay OBS15-135 Reexamination per Appendix Q and MRP-139 Category F requirements.

N/A N/A 2RY-01-S/PN-04-F4S 2RY-01-S 13R-08 UT NRI Safety A Nozzle-Safe End Overlay OBS15-137 Reexamination per Appendix Q and MRP-139 Category F requirements.

99.4% coverage in circ. direction and 99.2% in axial direction due to 2 laminar indications seen in the B2R13 baseline examination.

N/A N/A 2RY-01-S/PN-05-F5S 2RY-01-S 13R-08 UT NRI Safety B Nozzle-Safe End Overlay OBS15-138 Reexamination per Appendix Q and MRP-139 Category F requirements.

98.2% coverage in circ. direction and 98.3% in axial direction due to 1 laminar indication seen in the B2R13 baseline examination.

N/A N/A 2RY-01-S/PN-06-F6S 2RY-01-S 13R-08 UT NRI Safety C Nozzle-Safe End Overlay OBS15-141 Reexamination per Appendix Q and MRP-139 Category F requirements.

92.5% coverage in circ. direction and 90.9% in axial direction due to laminar indications seen in the B2R13 baseline examination.

13

7/29/2010

~Exelen..

- xIn Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Reactor Coolant System (RY)

,*Section I *,ComonentlD- o .. LiieNumber, &' , Relef ..Techncal hpActual',,-* Code Results Jrca. Descriptin , , .Requests Notes. Coverage:' Exam N/A N/A 2RY02A-6/J01S 2RY02A-6 13R-08 UT NRI PORV Nozzle - Elbow Overlay OBS15-171 Reexamination per Appendix Q requirements.

98.2% coverage in circ. direction and 98.4% in axial direction due to 1 laminar indication seen in the 82R13 baseline examination.

N/A N/A 2RY03AA-6/J01S 2RY03AA-6 13R-08 100 UT NRI Safety A Nozzle-Safe End - Elbow Overlay OBS15-160 Reexamination per Appendix Q requirements.

N/A N/A 2RY03AB-6/J01S 2RY03AB-6 13R-08 UT NRI Safety B Nozzle-Safe End - Elbow Overlay OBS15-164 Reexamination per Appendix Q requirements.

100% coverage in circ. direction and 99.1% in axial direction due to adjacent elbow configuration.

N/A N/A 2RY03AC-6/J01S 2RY03AC-6 13R-08 UT NRI Safety C Nozzle-Safe End - Elbow Overlay OBS15-168 Reexamination per Appendix 0 requirements.

99.6% coverage in circ. direction and 99.8% in axial direction due to laminar indications seen in the B2R13 baseline examination.

N/A N/A 2RY11A-14/J01S 2RY11A-14 13R-08 100 UT NRI Surge Nozzle Safe End - Pipe Overlay OBS15-144 Reexamination per Appendix 0 requirements.

R-A R1.11 2RY18A-2/W-01 2RY18A-2 13R-02 B9.40 VT-2 NRI Valve - Pipe 13T-01 13T-02 OBS15-001 R-A R1.11 2RY18A-2/W-02 2RY18A-2 13R-02 B9.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-002 R-A R1.11 2RY18A-2/W-03 2RY18A-2 13R-02 B9,40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-003 R-A R1.11 2RY18A-2/W-04 2RY18A-2 13R-02 B9.40 VT-2 NRI Pipe - WOL 13T-01 13T-02 OBS15-004 14

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Steam Generator (SG)

Section Xl. Component ID . Line Number Relief, -Techiaal, oCde I Actual* ,,IResults.,

Cat. Descripti on . Requests,  !; Notes* :Coverage d Exam.

Comments '

B15.120 2RC-01-BA/DRAIN 2RC-01-BA VT-2 NRI SG Channel Head Drain OBS15-211 Bare Metal exam per N-722 requirements. See WO#1 182319.

B15.120 2RC-01-BB/DRAIN 2RC-01-BB VT-2 NRI SG Channel Head Drain OBS15-214 Bare Metal exam per N-722 requirements. See WO#1 182320.

B15.120 2RC-01-BC/DRAIN 2RC-01-BC VT-2 NRI SG Channel Head Drain OBS15-215 Bare Metal exam per N-722 requirements. See WO#1 182321.

B15.120 2RC-01-BD/DRAIN 2RC-01-BD VT-2 NRI SG Channel Head Drain OBS15-216 Bare Metal exam per N-722 requirements. See WO#1 182317.

15

7/29/2010 Exelkn..

Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Safety Injection System (SI)

WSktion XI Cociiipqbhen ID~~ Line Nimb'ler 7Rei ef Tech~nical 064oce Actual iResults SD~sti~pin~ i Requests Notes, Coverage' Exam~

c~meisr.

B-K B10.20 2SI03DA-2/W-08A 2SI03DA-2 NA 100 PT IND Closure Plate 2RB-61 OBS15-204 1/16" Rounded Indication on penetration plate 0.2" from weld toe. Acceptable per procedure. Ref. RIR B2R15-PT-004.

C-C C3.20 2SI04B-12/C02 2SI04B-12 100 PT RI Closure Plate 2PC-66 PT RI PT RI PT NRI OBS15-203 One 0.1" rounded, one 1.3" linear, and one 2.4" linear indications. The linear indications are rejectable per procedure. Ref: IR 01057786. The indications were reexamined twice after minor surface conditioning.

Linear indications removed by blending and the areas were reexamined.

Additional examinations performed on 15-221 and 15-223.

C-C C3.20 2SI05BA-8/C02 2SI05BA-8 100 PT NRI Closure Plate 2PC-50 OBS15-221 WO# 01330141. Additional examination for OBS15-203.

R-A R1.11 2SI08HA-2/W-01 2SI08HA-2 13R-02 B9.40 VT-2 NRI Reducer - Coupling 13T-01 13T-02 OBS15-060 R-A R1.11 2SI08HA-2/W-02 2SI08HA-2 13R-02 B9.40 VT-2 NRI Coupling - Pipe 13T-01 13T-02 OBS15-061 R-A R1.11 2SI08HA-2/W-03 2SI08HA-2 13R-02 B9.40 VT-2 NRI Pipe - Flange 13T-01 13T-02 OBS15-062 R-A R1.11 2SI08HA-2/W-04 2SI08HA-2 13R-02 B9.40 VT-2 NRI Flange - Pipe 13T-01 13T-02 OBS15-063 R-A R1.11 2SI08HA-2/W-05 2SI08HA-2 13R-02 B9.40 VT-2 NRI Pipe - Coupling 13T-01 13T-02 OBS15-064 R-A R1.11 2SI08HA-2/W-06 2SI08HA-2 13R-02 89.40 VT-2 NRI Coupling - Reducer 13T-01 13T-02 OBS15-065 R-A R1.11 2SI08JA-1.5/W-01 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Reducer - Pipe 13T-01 13T-02 OBS15-066 16

7/29/2010 Exelein.

Byron Station Unit 2 B2R15 ISI Outage Report Weld I Component Outage Summary SYSTEM: Safety Injection System (SI)

Section Xl Component ID ,Line Number .Relief, 'Technical ,-Code Actual. Results' Cat Description v Requests, Notes , Coverage Exam Comments R-A R1.11 2SI08JA-1.5/W-02 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-067 R-A R1.11 2SI08JA-1.5/W-03 2SI08JA-1.5 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-068 R-A R1.11 2SI08JA-1.5/W-04 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-069 R-A R1.11 2SI08JA-1.5/W-05 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-070 R-A R1.11 2SI08JA-1.5NW-05A 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Pipe - Valve 13T-01 13T-02 OBS15-071 R-A R1.11 2SI08JA-1.5/W-05B 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Valve - Pipe 13T-61 13T-02 OBS15-072 R-A R1.11 2SI08JA-1.5/W-06 2SI08JA-1.5 13R-02 19.40 VT-2 NRI Pipe - Elbow 13T-01 13T-02 OBS15-073 R-A R1.11 2SI08JA-1.5/W-07 2SI08JA-1.5 13R-02 89.40 VT-2 NRI Elbow - Pipe 13T-01 13T-02 OBS15-074 R-A R1.11 2SI08JA-1.5/W-10 2SI08JA-1.5 13R-02 89.40 VT-2 NRI Pipe - Flange 13T-01 13T-02 OBS15-075 R-A R1.11 2SI08JA-1.5/W-11 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Flange - Pipe 13T-01 13T-02 OBS15-076 R-A R1.11 2SI08JA-1.5/W-14 2SI08JA-1.5 13R-02 89.40 VT-2 NRI Pipe - Coupling 13T-01 13T-02 OBS15-077 17

7/29/2010 Exelein.

Byron Station Unit 2 B2R15 ISI Outage Report Weld / Component Outage Summary SYSTEM: Safety Injection System (SI)

Section Xl, ComponentiD! , ,Lne Number.. Relief Techical Code , Actual Resultsn, Cat. Description, Requests - Notes,, Coverage " Exam Comme nts '

R-A R1.11 2SI08JA-1.5/W-15 2SI08JA-1.5 13R-02 B9.40 VT-2 NRI Coupling - Pipe 13T-01 13T-02 OBS15-078 18

7/29/2010 Exelon, Byron Station Unit 2 B2R15 ISI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM: Safety Injection System (SI)

CttmDescrption, Requests Notes Exami.

Commeýnts. -

I B-G-2 B7.50 2SI08HA-2/FLG 1-8 VT-1 RI Piping Flange Bolting OBS15-224 Flange was disassembled for gasket replacement under WO 01179198. All studs and nuts were reused.

1

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISl Outage Report Weld / Component Outage Summary (Preservice Inspections)

SYSTEM: Safety Injection System (SI)

Section Xl Component ID "Line Number , Relief, Technical Code Required Actual Results.

Cat. Item Description Notes

  • NRquests oCverage Exam Exam Comments NA NA 2SI18FC-2/W-01.02 2SI18FC-2 13R-02 B9.40 100 SURF PT NRI Valve - Pipe 13T-01 VT-2 VT-2 NRI 13T-02 Baseline examination Baseline exam of new socket weld W-4 under WO#01225344.

NA NA 2SI18FC-2/W-01A.01 2SI18FC-2 13R-02 B9.40 100 SURF PT NRI Pipe - Coupling 13T-01 VT-2 VT-2 NRI 13T-02 Baseline examination Baseline exam of new socket weld W-3A under WO#01225344.

NA NA 2SI18FC-2/W-O1B.01 2SI18FC-2 13R-02 B9.40 100 SURF PT NRI Coupling - Pipe 13T-01 VT-2 VT-2 NRI 13T-02 Baseline examination Baseline exam of new socket weld W-2 under WO#01225344.

1 7/29/2010

7/29/2010Ex

~Exelon, I In Byron Station Unit 2 B2R15 ISI Outage Report Detailed Inservice Inspection Bolts, Pumps, and Valves Listing (PSI)

SYSTEM: Reactor Coolant System (RY)

Section Xl, Component ID-, ei f Technical ActualT Results' Cat. Item Description Exam WRequeSt&"Noes Cohmments B-G-2 B7.50 2RY03BC-6/FLG 1-12 VT-1 NRI Piping Flange Bolting Baseline exam for 2RY8010C replacement under WO#01 178737.

B-G-2 B7.50 2RY76A-2/FLG 1-8 VT-1 NRI Piping Flange Bolting Baseline exam for flange bolting replacement under WO#01 180530.

1 7/29/2010

7/29/2010 Exelei n.

Byron Station Unit 2 B2R15 IS Outage Report Detailed Inservice Inspection Bolts, Pumps, and Valves Listing (PSI)

SYSTEM: Steam Generator (SG)

S component ID  : Relef; Technical Actuale Results Cat. Item IDescription -. RuesNos, Exa Comments B-G-2 B7.30 2RC-01-BA/BLT 1-32 VT-1 NRI SG Manway Studs and Nuts Baseline exam for Cold Leg Bolt #13 replacement. WO#01199605.

2 7/29/2010

7/29/2010 Exelkn..

Byron Station Unit 2 B2R15 ISI Outage Report Pressure Test Outage Summary SYSTEM: Auxiliary Feedwater System (AF)

Section Xl Component ID . .' , . Rehef, Techncal Actual, Results"'I Cat.' Item RequeSts Notes Exam Comments. '.

C-H C7.10 2-AF-2-1 13T-04 VT-2 NRI C-H C7.10 2-AF-2-2 13T-04 VT-2 NRI 1 7/29/2010

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report Pressure Test Outage Summary SYSTEM: Containment Spray System (CS) j.Sction.Xi Component ID., Techia "eif ~At~j esulti, Cat. Item " iequests':

N-tes Exam Comnments -

C-H C7.10 2-CS-2-1 13T-04 VT-2 NRI C-H C7.10 2-CS-2-2 13T-04 VT-2 NRI 2 7/29/2010

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report Pressure Test Outage Summary SYSTEM: Chemical & Volume Control System (CV)

Section X'I Component ID A Relief,ý41'Techinical Actual Results Cat. Item - Requests Notes Exam Comments C-H C7.10 2-CV-2-1 13T-04 VT-2 NRI C-H C7.10 2-CV-2-10 13T-04 VT-2 NRI C-H C7.10 2-CV-2-2 13T-04 VT-2 NRI C-H C7.10 2-CV-2-3 13T-04 VT-2 NRI C-H C7.10 2-CV-2-4 13T-04 VT-2 NRI C-H C7.10 2-CV-2-5 13T-04 VT-2 NRI C-H C7.10 2-CV-2-6 13T-04 VT-2 NRI C-H C7.10 2-CV-2-7 13T-04 VT-2 NRI 3 7/29/2010

7/29/2010 Exeln.,

Byron Station Unit 2 B2R15 ISI Outage Report Pressure Test Outage Summary.

SYSTEM: Fuel Pool Cooling System (FC)

Srestion XICompbnenti**D

.e*m .. . -equ Techniote .. ual Rgesult Cat., Itemn ýR-que-sts ~Notes ~ Exani Coiimmets' C-H C7.10 2-FC-2-1 13T-04 VT-2 NRI 4 7/29/2010

7129/2010 Exelan..

Byron Station Unit 2 B2R15 ISI Outage Report Pressure Test Outage Summary SYSTEM: Feedwater System (FW)

SeciohXI ornonetlDK -~ReieL~TeI~nca~ :A~tijI Resu'lts,

'Cat. -Item Reeest Noe~ xam~

Comments C-H C7.10 2-FW-2-2 13T-04 VT-2 NRI 5 7/29/2010

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report Pressure Test Outage Summary SYSTEM: Main Steam System (MS)

Section xI Component ID Relief. Technical ctua*A i Results

'Cat. Item Requests Notei :Exam Comments C-H C7.10 2-MS-2-1 13T-04 VT-2 NRI C-H C7.10 2-MS-2-2 13T-04 VT-2 NRI 6 7/29/2010

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISl Outage Report Pressure Test Outage Summary SYSTEM: Off Gas System (OG)

Section X1 i 1Component ID  : Relief Technca 4

Actual Results Cat.' item .. Requests Eam, E MNotes ComHments C-H 07.10 2-OG-2-1 13T-04 VT-2 NRI 7 7/29/2010

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report Pressure Test Outage Summary SYSTEM: Process Sampling System (PS)

Section Xl. Component ID' ,-jiefjechnical "i Actual Results

  • Cat IeRequeist 9 otes Exam Comments' C-H C7.10 2-PS-2-3 13T-04 VT-2 NRI C-H C7.10 2-PS-2-4 13TZ04 VT-2 NRI C-H C7.10 2-PS-2-5 13T-04 VT-2 NRI C-H C7.10 2-PS-2-6 13T-04 VT-2 NRI 8 7/29/2010

7/29/2010 Exelmn.

Byron Station Unit 2 B2R15 ISI Outage Report Pressure Test Outage Summary SYSTEM: Reactor Coolant System (RC)

..Section Xl ID ,. Relief AComp'onent Results

'TechniCal,.*-c.

Cat. Item Requests Notes Ex,am Comments B-P B15.10 2-RC-1-1 13T-04 VT-2 NRI 9 7/29/2010

7/29/2010 Exelkn.,

Byron Station Unit 2 B2R15 ISI Outage Report Pressure Test Outage Summary SYSTEM: Residual Heat Removal System (RH)

Section xIComponent ID. '*.. r " R elief. Technical Actual Results

/ Cat. Item . ... ... ,,,  :: . . , .. .. . -  ;- ]Requests,, ,,Notes - . . Exam I Ciomments C-H C7.10 2-RH-2-1 13T-04 VT-2 NRI C-H C7.10 2-RH-2-2 13T-04 VT-2 NRI C-H C7.10 2-RH-2-3 13T-04 VT-2 NRI C-H C7.10 2-RH-2-6 13T-04 VT-2 NRI 10 7/29/2010

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISl Outage Report Pressure Test Outage Summary SYSTEM: Safety Injection System (SI)

Section XI Component ID,. .. " Reief 'Technical Actual Results.

Cat. Item..qess Notes Exam' Comments C-H C7.10 2-SI-2-1 13T-04 VT-2 NRI C-H C7.10 2-SI-2-2 13T-04 VT-2 NRI C-H C7.10 2-SI-2-3 13T-04 VT-2 NRI C-H C7.10 2-SI-2-4 13T-04 VT-2 NRI C-H C7.10 2-SI-2-5 13T-04 VT-2 NRI C-H C7.10 2-SI-2-6 13T-04 VT-2 NRI C-H C7.10 2-SI-2-7 13T-04 VT-2 NRI 11 7/29/2010

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report Pressure Test Outage Summary SYSTEM: Essential Service Water System (SX)

Section -X C0omlonent ID .' -' Relief 'Technical Actual Results Cat. Item "equests 'Notes Exam Com m ents.

C-H C7.10 2-SX-2-1 13T-04 VT-2 NRI C-H C7.10 2-SX-2-2 13T-04 VT-2 NRI 12 7/29/2010

7/29/2010 E e~ n Byron Station Unit 2 B2R15 ISI Outage Report Component Support Outage Summary SYSTEM: Containment Spray System (CS)

Section Xl" Component ID -'i. ne Number' Relief Technical A"ctual*. .Results Cat. Item IDescription Requests Notes Exam Comments F-A F1.20 2CS02AA- 10/2CS03A007S 2CS02AA-10 VT-3 NRI SNUBBER- SR MINOR SURFACE RUST ON REAR BRACKET WELDS AND PIVOT PIN, NO DEGRADATION NOTED F-A F1.20 2CS06AA-6/2CS06033A 2CS06AA-6 VT-3 NRI ANCHOR No indication detected 1

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISl Outage Report Component Support Outage Summary SYSTEM: Chemical & Volume Control System (CV)

Section Xl jcomponent ID - Lihe Number o . Relief, Technicai A0U01-:- Results Cat. Item oDescription Requests, Notes ,- *m Comments F-A F1.20 2CV05CB-6/2CV08007V 2CV05CB-6 VT-3 NRI VARIABLE ALL WELDS ARE PAINTED F-A F1.20 2CV09A-4/2CV01A064X 2CV09A-4 VT-3 NRI SEISMIC WELDS ARE PAINTED F-A Fl1I0 2CV10DB-3/2CV02009S 2CV10DB-3 VT-3 NRI SNUBBER SR INSULATION REMOVED FOR EXAM F-A F1.10 2CV45B-2/2CV22007X 2CV45B-2 VT-3 NRI SEISMIC INSULATION REMOVED FOR EXAM F-A F1.10 2CV45B-2/2CV22008X 2CV45B-2 VT-3 NRI SEISMIC INSULATION REMOVED FOR EXAM F-A F1.10 2CV45B-2/2CV22010X 2CV45B-2 VT-3 NRI SEISMIC INSULATION REMOVED FOR EXAM F-A F1.10 2CV45B-2/2CV22011X 2CV45B-2 VT-3 NRI SEISMIC INSULATION REMOVED FOR EXAM F-A F1.10 2CV45B-2/2CV22016A 2CV45B-2 VT-3 NRI ANCHOR INSULATION REMOVED FOR EXAM F-A F1.10 2CVA6AA-2/2CV09026S 2CVA6AA-2 VT-3 NRI SNUBBER SR INSULATION REMOVED FOR EXAM F-A F1.10 2CVA7AA-2/2CV25012S 2CVA7AA-2 VT-3 NRI SNUBBER SR Insulation removed for exam.

F-A F1.10 2CVB7A-3/2CV06005X 2CVB7A-3 VT-3 NRI SEISMIC NONE 2

7/29/2010 Exel in ,

Byron Station Unit 2 B2R15 ISl Outage Report Component Support Outage Summary SYSTEM: Feedwater System (FW)

Section ,XI., , I pm,6m nent ID *,*,,* Ž,1,:_

,, ,:,lineNumbe- ,,,,* ,***..

  • K:*

.R.,ehe~f4 *,,Techniical: j,*,Actual ,.,, *Results, Cat. IteM, .ielcrppflonl 7>:-, /iIqet8*oes!:Exrn Commen s ' --

F-A F1.20 2FW03DA-16/2FW02016S 2FW03DA-16 VT-3 NRI SNUBBER SR F-A F1 .20 2FW03DA-16/2FW02020X 2FW03DA-16 VT-3 NRI SEISMIC NONE F-A F1.20 2FW03DB- 16/2FW03017S 2FW03DB- 16 VT-3 NRI SNUBBER SR INSULATION REMOVED FOR EXAM F-A F1 .20 2FW03DD-16/2FW05022S 2FW03DD-16 VT-3 NRI SNUBBER SR F-A F1.20 2FW81AA-6/2AF06038R 2FW81 AA-6 VT-3 NRI RIGID NONE F-A F1 .20 2FW81 BA-6/2AF06040V 2FW81 BA-6 VT-3 NRI VARIABLE F-A F1 .20 2FW87CC-6/2FW08005S 2FW87CC-6 VT-3 NRI SNUBBER SR GRADING REMOVED FOR EXAM 3

7/29/2010 Exelen.

Byron Station Unit 2 B2R15 ISI Outage Report Component Support Outage Summary SYSTEM: Main Steam System (MS)

Section X1 Crpanen 'ID' ' ""-V1 Lirei"Ndmberý ý(R~if ,Atl.

.Tecnica lRe6ts 'It cat, lIemf~ n9 bescri~toV 'No RW f xa j F-A F1.20 2MS07AA-28/2MS01205X 2MS07AA-28 VT-3 NRI SEISMIC NONE F-A F1.20 2MS07AC-28/2MS01 101S 2MS07AC-28 DBL VT-3 NRI SNUBBER SR

  • S/N# 13772 ($1) 3-7/8" - S/N# 13785 (S2) 3-5/8" 4

7/29/2010 Exel mn..

Byron Station Unit 2 B2R15 ISI Outage Report Component Support Outage Summary SYSTEM: Reactor Coolant System (RC)

Section XI ComponentlD" Line Number Relief of!-o Technical Actual Results Cat. Item IDescription Requests Noes Eam Comments F-A F1.10 2RC14AB-2/2CV15016V 2RC14AB-2 VT-3 NRI VARIABLE F-A Fl.10 2RC14AD-2/2CV25019S 2RC14AD-2 VT-3 NRI SNUBBER SR Insulation removed for exam, snubber was removed for functional testing at time of exam. Pipe clamp and structural steel examined.Snubber exam performed on report 2010-EPP-025.

F-A F1.10 2RC14AD-2/2CV25020S 2RC14AD-2 VT-3 NRI SNUBBER SR Insulation removed for exam, snubber was removed for functional testing at time of exam. Pipe clamp and structural steel examined.

Snubber exam performed on report 201 0-EPP-023.

F-A F1.10 2RC14AD-2/2CV25024S 2RC14AD-2 VT-3 NRI SNUBBER SR Insulation removed for exam, snubber was removed for functional testing at time of exam. Pipe clamp and structural steel examined.

Snubber exam performed on report 201 0-EPP-026.

F-A Fl.10 2RC22AA-1.5/2RC16001S 2RC22AA-1-1/2 VT-3 NRI SNUBBER SR INSULATION REMOVED FOR EXAM 5

7/29/2010. Exelon.,

Byron Station Unit 2 B2R15 ISI Outage Report Component Support Outage Summary SYSTEM: Residual Heat Removal System (RH)

Sepction XI.', Linee Number _ ; r Relief- Technical Ata0 Results CatIem Description, Reuets Notes Exam Com ments -

F-A F1.20 2RH01CA-16/2SI06259X 2RH01CA-16 VT-3 NRI SEISMIC No indication detected 6

7/29/2010 ExeI n.

Byron Station Unit 2 B2R15 ISI Outage Report Component Support Outage Summary SYSTEM: Reactor Coolant System (RY)

SectionXl , c0PornentD Line Numl*er Reliefi', Technical Actual Results Ickrto ., eeuests Nes Ea Commentfs F-A F1.40 2RY-01-S/SKT 2RY-01-S VT-3 NRI PRESSURIZER SKIRT F-A F1.10 2RY18A-2/2RY06114S 2RY18A-2 VT-3 NRI SNUBBER SR INSULATION REMOVED FOR EXAM 7

7/2912010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report Component Support Outage Summary SYSTEM: Safety Injection System (SI)

Section Xl ComponentlD . Lin~e'Nme Rel ief~ , ehicl At'a esults Cat. Item IDescription Rque'sts, Notes Ea Comments F-A Fl.20 2SI04B-12/2RH02109X 2SI04B-l 2 VT-3 NRI SEISMIC F-A Fl.20 2SI04B-12/2RHO211OX 2S10413-12 VT-3 NRI SEISMIC F-A Fl.10 2SI04D-8/2RH02020X 2SI04D-8 VT-3 NRI SEISMIC F-A F1.20 2SI05CA-8/2SI01024X 2SI05CA-8 VT-3 NRI SEISMIC F-A Fl.20 2SI05CA-8/2SI01040X 2SI05CA-8 VT-3 NRI SEISMIC F-A F1.20 2SI06BA-24/2SI06260X 2SI06BA-24 VT-3 NRI SEISMIC No indication detected F-A Fl.20 2SI06BA-24/2SI06261X 2SI06BA-24 VT-3 NRI SEISMIC No indication detected F-A Fl.10 2SI08FA-3/2SI21014X 2SI08FA-3 VT-3 NRI SEISMIC F-A F1.10 2SI08HA-2/2SI25009X 2S108HA-2 VT-3 NRI SEISMIC 8

7/29/2010 ExelonI Byron Station Unit 2 B2R15 ISI Outage Report Component Support Outage Summary SYSTEM: Essential Service Water System (SX)

Section X mot 'ID Lne Number Relief 'r TechnicaIk Actual Results-'

A 'D sri~ji on Reques~ts , ots C men s - ... , .

F-A F1.20 2SX06CA-14/2SX06009X 2SX06CA-14 VT-3 NRI.

SEISMIC F-A F1.20 2SX06EC-10/2SX06023A 2SX06EC 10 VT-3 NRI ANCHOR INSIDE RCFC PLENIUM F-A F1.20 2SX07EB-14/2SX09015X 2SX07EB- 14 VT-3 NRI SEISMIC 9

7/29/2010 Exelkn.

Byron Station Unit 2 Byron Station Outage B2R15 Snubber Outage Summary (Page 1 of 11)

SYSTEM: Auxiliary Feedwater System (AF)

!§cioin.X,)(. ',2CtnhjpnentID7 Li'~br Relif2' 'TechnicalY i-AtuaIl ResuIlts',

F-A F1.20 2FW87BC-3/2FW10001S 2FW87BC-3 VT-3 NRI SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 1

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Byron Station Unit 2

.Byron Station Outage B2R15 Snubber Outage Summary (Page 2 of 11)

SYSTEM: Containment Spray System (CS)

Section Xl Component ID Line Number - Relief Technical Actual Results Cat. Item IDescription Requests Notes Exam Comments .

F-A F1.20 2CS02AB-1 0/2CS03B01 8S 2CS02AB-10 VT-3 NRI SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 2

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Byron Station Unit 2 Byron Station Outage B2R15 Snubber Outage Summary (Page 3 of 11)

SYSTEM: Chemical & Volume Control System (CV) setin L> C onent~~, Actual~

C ~ Dscription

[It

);qk Rqet Nt~ M NA NA 2CV10B-3/2CV04002S 2CV10B-3 VT-3 NRI SNUBBER SR FT PASS NA NA 2CV10BL3/2CV04012S 2CV 10B-3 VT-3 NRI SNUBBER SR FT PASS NA NA 2CV10CA-3/2CV22002S 2CV 10CA-3 VT-3 NRI SNUBBER SR FT PASS NA NA 2CV 15AC-3/4/2CV29002S 2CV15AC-3/4 VT-3 NRI SNUBBER SR FT PASS NA NA 2CVB7BA-3/2CV23005S 2CVB7BA-3 VT-3 NRI SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 3

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Byron Station Unit 2 Byron Station Outage B2R15 Snubber Outage Summary (Page 4 of 11)

SYSTEM: Feedwater System (FW)

Section Xl Component11) ,D Line Number Relief Technical ýj Actual, Results S~~at.~ Itm 'ecito~s otes, E"r xam,ý'

F-A F1.20 2FW03DA-16/2FW02012S 2FW03DA-16 VT-3 NRI SNUBBER SR F-A F1 .20 2FW87CC-6/2FW08005S 2FW87CC-6 VT-3 NRI SNUBBER SR FT PASS F-A F1 .20 2FW87CC-6/2FW08006S 2FW87CC-6 VT-3 NRI SNUBBER SR FT PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 4.

7/29/2010 Exelein.

Byron Station Unit 2 Byron Station Outage B2R15 Snubber Outage Summary (Page 5 of 11)

SYSTEM: Main Steam System (MS)

Section Xl Component ID Line Number Technical Actual Results Cat. Item Description Requests Notes Exam Comments .

N/A SNUB 2MS01AC-32.75/2MS07006-S1 2MS01AC-32.75 DBL VT-3 NRI SNUBBER SR FT PASS N/A SNUB 2MS01AC-32.75/2MS07006-S2 2MS01AC-32.75 DBL VT-3 NRI SNUBBER SR FT PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-1 220 and IWF-2500 tables 5

7/29/2010ExIn Byron Station Unit 2 Byron Station Outage B2R15 Snubber Outage Summary (Page 6 of 11)

SYSTEM: Reactor Coolant System (RC) ac Item X Cescrpb oiD~n' . . . . . ... Requ*sts N-.

ot"-": "...........

rnmnts.

F-A F1.40 2RC01BA-2A/2RC01BA-A 2RC01 BA-2A VT-3 NRI SNUBBER SR F-A F1.40 2RC01BA-2A/2RC01BA-B 2RC01BA-2A VT-3 NRI SNUBBER SR F-A F1.40 2RC01BB-2B/2RC01BB-A 2RC01 BB-2B VT-3 NRI SNUBBER SR FT PASS F-A F1.40 2RC01BB-2B/2RC01BB-B 2RC01 BB-2B VT-3 NRI.

SNUBBER SR F-A F1.40 2RC01BC-2C/2RC01BC-A 2RC01 BC-2C VT-3 NRI SNUBBER SR SNUBBER FT FAIL F-A F1.40 2RC01BC-2C/2RC01BC-B 2RC01 BC-2C VT-3 NRI SNUBBER SR SNUBBER FT PASS F-A F1.40 2RC01BD-2D/2RC01BD-A 2RC01 BD-2D VT-3 NRI SNUBBER SR F-A F1.40 2RC01BD-2D/2RCO1BD-B 2RC01BD-2D VT-3 NRI SNUBBER SR NA NA 2RC08AA-3/4/2RC1 6009S 2RC08AA-3/4 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 2RC13AB-2/2CV15002S 2RC13AB-2 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 2RC14AD-2/2CV25019S 2RC14AD-2 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 2RC14AD-2/2CV25020S 2RC14AD-2 VT-3 NRI" SNUBBER SR FT PASS F-A F1.10 2RC14AD-2/2CV25024S 2RC14AD-2 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 2RC22AA-1.5/2RC16011S 2RC22AA-1-1/2 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 2RC22AB-1.5/2RC17015S 2RC22AB-1-1/2 VT-3 NRI SNUBBER SR FT PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 6

7/29/2010 Exelkn.

Byron Station Unit 2 Byron Station Outage B2R15 Snubber Outage Summary (Page 7 of 11)

SYSTEM: Reactor Coolant System (RC)

Section XI Component ID Line Number - . Relief Technical Actual Results Cat. Item Description - Requests,. Notes Exam Comments ' .

NA NA 2RC48BB-1/2/2RC90B008S 2RC48BB-1/2 VT-3 NRI SNUBBER SR FT PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 7

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Byron Station Unit 2 Byron Station Outage B2R15 Snubber Outage Summary (Page 8 of 11)

SYSTEM: Residual Heat Removal System (RH)

Section XI lComponent ID Line Number . Relief Technical Actual, I-Results Cat. Item Description "ores',

Notequesis ýxam-Comments F-A F1.20 2RH02AA-8/2RH07003S 2RH02AA-8 VT-3 NRI SNUBBER SR FT PASS F-A F1.20 2RH02AA-8/2RH07012S 2RH02AA-8 VT-3 NRI SNUBBER SR FT PASS NA NA 2RH26AA-3/4/2RH02121S 2RH26AA-3/4 VT-3 NRI SNUBBER SR FT PASS Note: Section X1 Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 8

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Byron Station Unit 2 Byron Station Outage B2R15 Snubber Outage Summary (Page'9 of 11)

SYSTEM: Reactor Coolant System (RY)

Section Xl Component ID Line Number Relief Technical :Actual Results Cat. Item IDescription 4rr  : Requests Notes Exar . .

CornmentsAl N/A SNUB 2RY01B-6/2RY06025-S1 2RY01B-6 DBL VT-3 NRI SNUBBER SR FT PASS N/A SNUB 2RY01 B-6/2RY06025-S2 2RY01 B-6 DBL VT-3 NRI SNUBBER SR FT PASS F-A F1.10 2RY02B-3/2RY09077S 2RY02B-3 VT-3 NRI SNUBBER SR FT PASS NA NA 2RY34AB-1/2/2RC92002S 2RY34AB-1/2 VT-3 NRI SNUBBER SR FT PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 9

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Byron Station Unit 2 Byron Station Outage B2R15 Snubber Outage Summary (Page 10 of 11)

SYSTEM: Steam Generator Blowdown System (SD)

Section XI Component ID Line Number Relief Technicald Actual Results Cat. Item IDescription Requests Notes Exam Comments, '  ;

NA NA 2SD01CB-2/2SD01005S 2SD01CB-2 VT-3 NRI SNUBBER SR FT PASS Note: Section Xl Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 10

7/29/2010 Exelkn,.

Byron Station Unit 2 Byron Station Outage B2R15 Snubber Outage Summary (Page 11 of 11)

SYSTEM: Safety Inhection System (SI)

Section X I Component ID Line Number Technical Actual Results Cat. Item IDescription Requests Notes Exam, Comments N/A SNUB 2SI05DC-6/2SI09014-S1 2SI05DC-6 DBL VT-3 NRI SNUBBER SR FT PASS N/A SNUB 2SI05DC-6/2SI09014-$2 2S105DC-6 DBL VT-3 NRI SNUBBER SR FT PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 11

SECTION 3.0 (This report is used to verify that the periodic BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTION XI (The percentage requirements of Tables IWx-requirements of Tables IWx-2412-1 will be met by EXAMINATION STATUS REPORT 2412-1 apply to the Category and were the interval schedule.) applied to each Item only when practical.)

  1. of Total # Exams Completed  % Exams Completed Item No. Comp Selected Mi Per 1 Max Min Per 2 Max Per 3  % Selected Period 1 Period 2 Period 3 Category B-A Non-Deferred Exams B1.30 1 1 0 1 1 1 0 1 0 100.00% 100.00% 100.00% 100.00%

B1.40 1 1 0 0 1 1 0 1 0 100.00% 0.00% 0.00% 0.00%

Totals: 2 2 0 1 1 1 0 1 0 100.00% 50.00% 50.00% 50.00%

Category B-A Deferred Exams-B1.11 3 3 N/A 3 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%

B1.21 2 2 N/A 1 N/A N/A 0 N/A 0 100.00% 50.00% 50.00% 50.00%

Totals: 5 5 N/A 4 N/A N/A 0 N/A 0 100.00% 80.00% 80.00% 80.00%

1. (B1.11 & B1.21) Examination completion exceeds 50.00% for 1 st Period and 75.00% for this 2 nd Period. The examinations were performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.

Category B-B Non-Deferred Exams B2.11 2 2 0 0 1 1 1 1 0 100.00% 0.00% 50.00% 50.00%

B2.12 2 2 0 0 1 1 1 1 0 100.00% 0.00% 50.00% 50.00%

B2.40 4 1 0 1 1 1 0 1 0 25.00% 100.00% 100.00% 100.00%

Totals: 8 5 1 1 2 2 2 2 0 62.50% 20.00% 65.00% 65.00%

1. (B2.40) Per Examination Category'B-B, Note 1, examinations may be limited to one vessel among a group of vessels performing a similar function.

Category B-D Non-Deferred Exams B3.110 6 6 1 1 3 2 3 3 0 100.00% 16.67% 66.67% 66.67%

B3.120 6 6 1 1 3 2 4 3 0 100.00% 16.67% 66.67% 66.67%

B3.140 8 8 .2 4 4 0 0 2 0 100.00% 50.00% 50.00% 50.00%

Totals: 20 20 4 6 10 4 7 9 0 100.00% 30.00% 65.00% 65.00%

1. (B3.120 & B3.140) Per 10 CFR 50.55a(b)(2)(xxi)(A), Table IWB-2500-1 examination requirements, the provisions of Table IWB-2500-1, Examination Category B-D, Item Numbers B3.120 and B3.140 in the 1998 Edition must be applied when using the 1999 Addenda through the latest edition and addenda.

Category B-D Deferred Exams B3.90 8 8 N/A 8 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%

B3.100 8 8. N/A 8 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%

Totals: 16 16 N/A 16 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%

1. (B3.100) This Item Number requires a visual examination with enhanced magnification in lieu of volumetric examination, as allowed by Code Case N-648-1.

Section 3.0 Page 1 of 7

(This report is used to verify that the periodic BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTION X1 (The percentagerequirementsof Tables JWx-requirements of Tables IWx-2412-1 will be met by EXAMINATION STATUS REPORT 2412-1 apply to the Category and were the interval schedule.) applied to each Item only when practical.)

I  % Exams Completed

  1. of Total # Exams Completed Item No. Comp Selected Mi Per 1 Max Min Per 2 Max Per 3  % Selected Period 1 Period 2 Period 3
2. (B3.90 & B3.100) Per Examination Category B-D, Note 5, for PWR's in the second and successive inspection intervals, these examinations may be deferred to the end of the interval provided no repair/replacement activities have been performed on the examination item, and no flaws or relevant conditions requiring successive inspections in accordance with IWB-2420(b) are contained in the examination item.
3. (B3.90 & B3.100) Examination completion exceeds 50.00% for 1st Period and 75.00% for this 2 nd Period. The examination were performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.

Category B-G-1 Deferred Exams B6.10 3 3 N/A 3 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%

B6.20 3 3 N/A 3 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%

B6.40 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00%

B6.50 3 3 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00%

B6.170 1 1 N/A 0 N/A N/A 0 N/A 0 100.00% 0.00% 0.00% 0.00%

B6.180 4 1 N/A 0 N/A N/A 0 N/A 0 25.00% 0.00% 0.00% 0.00%

B6.190 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%

B6.210 8 2 N/A 0 N/A N/A 0 N/A 0 25.00% 0.00% 0.00% 0.00%

B6.220 8 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%

B6.230 8 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%

Totals: 43 14 N/A 6 N/A N/A 0 N/A 0 32.56% 42.86% '42.86% 42.86%

1. (B6.10 & B6.20 & B6.50) Single components representing one third of the 54 Reactor Vessel Closure Head Nuts, Closure Studs, and Closure Washers, Bushings. The examinations were performedat the beginning of the Inspection Interval as allowed by Relief Request 13R-01.
2. (B6.40) A single component representing all of the 54 Reactor Vessel Threads in Flange to be examined.
3. (B6.170) A single component represents the five sets of CETC column nuts.
4. (B6.180) Four components are tracked in the database, each representing one of the 24 Bolts on one of the four Reactor Coolant Pumps (96 total) as reported in the ISI Program Plan. The volumetric examination of these components is limited to only one of the pumps per Examination Category B-G-1, Note 3 and Examination Category B-L-2, Note 1. Examination is required only once per inspection interval.
5. (B6.190) Four components are tracked in the database, each representing all 24 associated Flange Surfaces and Nuts, Bushings, and Washers for one of the four Reactor Coolant Pumps (96 total) as reported in the ISI Program Plan. The visual examination of these components is limited to only one of the pumps per Examination Category B-G-1, Note 3 and Examination Category B-L-2, Note 1. Also, per Examination Category B-G-1, Note 4 and Examination Category B-L-2, Note 2, examination is required only when a pump is disassembled for maintenance, repair, or volumetric examination or bolting is removed.

Examination is required only once per inspection interval.

6. (B6.210) Eight components are tracked in the database, each representing all of the Bolts and associated Nuts, Bushings, and Washers and Flange Surfaces on one of the eight Reactor Coolant Valves as reported in the ISI Program Plan. The volumetric examination of these components is limited to only one of the valves per Examination Category B-G-1, Note 3 and Examination Category B-M-2, Note 3. Examination is required only once per inspection interval.

Section 3.0 Page 2 of 7

(This report is used to verify that the periodic BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTION XI (The percentage requirements of Tables lWx-requirements of Tables IWx-2412-1 will be met by EXAMINATION STATUS REPORT 2412-1 apply to the Category and were the interval schedule.) I applied to each Item only when practical.)

  1. of Total # Exams Completed  % Exams Completed Item No. Comp Selected Mi Per I Max Min Per 2 Max Per 3  % Selected Period 1 Period 2 Period 3
7. (B6.220 & B6.230) Eight components are tracked in the database, each representing all of the Bolts and associated Nuts, Bushings, and Washers and Flange Surfaces on one of the eight Reactor Coolant Valves as reported in the ISI Program Plan. The visual examination of these components is limited to only one of the valves per Examination Category B-G-1, Note 3 and Examination Category B-M-2, Note 3. Also, per Examination Category B-G-1, Note 4 and Examination Category B-M-2, Note 2, examination is required only when a valve is disassembled for maintenance, repair, or volumetric examination or bolting is removed.

Examination is required only once per inspection interval.

Category B-G-2 Deferred Exams B7.10 2 1 N/A 0 N/A N/A 0 N/A 0 50.00% 0.00% 0.00% 0.00%

B7.20 1 0 N/A. 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%

B7.30 4 4 N/A 2 N/A N/A 0 N/A 0 100.00% 50.00% 50.00% 50.00%

B7.50 20 5 N/A 3 N/A N/A 1 N/A 0 25.00% 60.00% 80.00% 80.00%

B7.60 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%

B7.70 26 1 N/A 1 N/A N/A 0 N/A 0 3.85% 100.00% 100.00% 100.00%

Totals: 57 11 N/A 6 N/A N/A 1 N/A 0 19.30% 54.55% 63.64% 63.64%

1. (B7.10) Two components representing the CETC and RVLIS Clamp Bolts and associated Nuts as reported in the ISI Program Plan.
2. (B7.20) A single component representing all 16 Pressurizer Manway Bolts and associated Nuts as reported in the ISI Program Plan.
3. (B7.30) Four components are tracked in the database, each representing all 32 Bolts and associated Nuts for both Manways on each of the four Steam Generator (128 total) as reported in the ISI Program Plan.
4. (B7.50) Per Examination Category B-G-2, Note 3, examination is required only when a bolted connection is disassembled or bolting is removed. Also, per Examination Category B-G-2, Note 3, examinations are limited to at least one bolted connection within each group of bolted connections that are similar in design, size, function, and service. Examination is required only once per inspection interval within each bolted connection group.
5. (B7.60) Four components are tracked in the database, each representing all 36 Bolts and associated Nuts for one of the four Reactor Coolant Pumps (144 total) as reported in the ISI Program Plan. Per Examination Category B-G-2, Note 2 and Examination Category B-L-2, Note 2, examination is required only when a pump is disassembled for maintenance, repair, or volumetric examination or bolting is removed. Also, per Examination Category B-G-2, Note 2 and Examination Category B-L-2, Note 1, examinations are limited to at least one pump within each group of pump that are of the same size, design, manufacturing method, and function. Examination is required only once per inspection interval within each valve group.
6. (B7.70) Per Examination Category B-G-2, Note 2 and Examination Category B-M-2, Note 2, examination is required only when a valve is disassembled for maintenance, repair, or volumetric examination or bolting is removed. Also, per Examination Category B-G-2, Note 2 and Examination Category B-M-2, Note 3, examinations are limited to at least one valve within each group of valves that are of the same size, design, manufacturing method, and function. Examination is required only once per inspection interval within each valve group.

Section 3.0 Page 3 of 7

(This report is used to verify that the periodic BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTION Xl (The percentage requirements of Tables IWx-

.requirements of Tables IWx-2412-1 will be met by EXAMINATION STATUS REPORT 2412-1 apply to the Category and were the interval schedule.) I ........... .. ... ... .. applied to each Item only when practical.)

  1. of Total # Exams Comrleted  % Exams Corpleted Item No. Comp Selected Min Per 1 Max Min Per 2 Max Per 3 %Selected Period 1 Period 2 Period 3 Category B-K Non-Deferred Exams B10.10 2 2 0 0 1 1 0 1 0 100.00% 0.00% 00.00% 0.00%

B10.20 8 3 1 1 1 1 1 1 0 37.50% 33.33% 66.67% 66.67%

Totals: 10 5 1 1 2 2 1 2 0 50.00% 20.00% 40.00% 40.00%

1. (B10.10) Per Examination Category B-K, Note 4, for multiple vessels of similar design, function and service, only one welded attachment of only one of the multiple vessels shall be selected for examination. Conservatively, a welded attachment of each type of welded attachment of one of multiple vessels will be examined.
2. (B10.20) Per Examination Category B-K, Note 5, for piping, pumps, and valves, a sample of 10% of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined. This requirement is conservatively interpreted to mean that 10% of the total Category B-L-2 Deferred Exams B12.20 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%

Totals: 4 0 N/A 0 N/A N/A 0 N/A 0 0.00% 0.00% 0.00% 0.00%

1. (B12.20) The examination of pump casings is limited to only one of the pumps performing similar functions in the system per Examination Category B-L-2, Note
1. Also, per Examination Category B-L-2, Note 2, examination is required only when a pump is disassembled for maintenance, repair, or volumetric examination. Examination is required only once per inspection interval.

Category B-M-2 Deferred Exams B12.50 37 2 N/A 2 N/A N/A 0 N/A 0 5.41% 100.00% 100.00% 100.00%

Totals: 37 2 N/A 2 N/A N/A 0 N/A 0 5.41% 100.00% 100.00% 100.00%

1. (B12.50) Per Examination Category B-M-2, Note 2, examination is required only when a valve is disassembled for maintenance, repair, or volumetric examination. Also, per Examination Category B-M-2, Note 3, examinations are limited to at least one valve within each group of valves that are of the same size, design, manufacturing method, and function. Examination is required only once per inspection interval within each valve group.

Category B-N-1 Non-Deferred Exams B13.10 2 1 0 1 1 1 0 50.00% 100.00% 200.00% 200.00%

Totals: 2 1 0 1 1 1 1 1 0 50.00% 100.00% 200.00% 200.00%

1. (B13.10) "% Completed" exceeds 100% since the vessel interior is selected for examination once each period (three times during the interval).

Section 3.0 Page 4 of 7

I (This report is used to verify that the periodic BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTION XI (The percentage requirements of Tables IWx-requirements of Tables IWx-2412-1 will be met by 2412-1 apply to the Category and were EXAMINATION STATUS REPORT the interval schedule.) -. . . . . . . . I applied to each Item only when practical.)

  1. of Total # Exams Completed  % Exams Completed Item No. Comp Selected Min Per 1 Max Min Per 2 Max Per 3  % Selected Period 1 Period 2 Period 3 Category B-N-2 Deferred Exams B13.50 1 1 N/A 1 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%

B13.60 1 1 N/A 1 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%

Totals: 2 2 N/A 2 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%

1. (B13.50 & B13.60) Examination completion exceeds 50.00% for 1st Period and 75.00% for this 2nd Period. The examination were performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.

Category B-N-3 Deferred Exams B13.70 1 1 N/A 1 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%

Totals: 1 1 N/A 1 N/A N/A 0 N/A 0 100.00% 100.00% 100.00% 100.00%

1. (B133.70) Examination completion exceeds 50.00% for 1 st Period and 75.00% for this 2 nd Period. The examination were performed at the beginning of the Inspection Interval as allowed by Relief Request 13R-01.

Category B-O Deferred Exams B14.10 5 5 N/A 2 N/A N/A 0 N/A 0 100.00% 40.00% 40.00% 40.00%

Totals: 5 5 N/A 2 N/A N/A 0 N/A 0 100.00% 40.00% 40.00% 40.00%

1. (B134.10) 10% of the 45 CRD Housings (as reported in the ISI Program Plan) are required to be examined each interval per this Item Number. These 5 components represent that 10% population.

Category B-P Non-Deferred Exams B15.10 1 1 N/A 2 N/A N/A 1 N/A 0 100.00% 200.00% 300.00% 0.00%

Totals: 1 1 N/A 2 N/A N/A 1 N/A 0 100.00% 200.00% 300.00% 0.00%

1. (B135.10) "% Completed" exceeds 100% since Class 1 pressure tests are performed each refueling outage.
2. (B15.10) One component representing the five systems in Class 1 as reported in the ISI Program Plan.

Category C-A Non-Deferred Exams C1.10 14 3 1 1 1 1 0 1 0 21.43% 33.33% 33.33% 33.33%

C1.20 6 1 0 0 1 1 0 1 0 16.67% 0.00% 0.00% 0.00%

C1.30 4 1 0 1 1 1 0 1 0 25.00% 100.00% 100.00% 100.00%

Totals: 24 5 1 2 2 1 0 1 0 20.83% 40.00% 40.00% 40.00%

1. (C1.104& C1.20) Per Examination Category C-A, Note 3, in the case of multiple vessels of similar design, size, and service, the required examinations may be limited to one vessel or distributed among the vessels.

Section 3.0 Page 5 of 7

(This report is used to verify that the periodic BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTION XI (The percentage requirements of Tables IWx-requirements of Tables (Wx-2412-1 will be met by EXAMINATION STATUS REPORT 2412-1 apply to the Category and were the interval schedule.) ..... .. . . . . . . . . I applied to each Item only when practical.)

  1. of T Total # Exams Completed  % Exams Completed Item No. Comp Selected Mi Per 1 Max Min Per 2 Max Per 3  % Selected Period 1 Period 2 Period 3 Category C-B Non-Deferred Exams C2.21 16 3 1 1 1 1 0 1 0 18.75% 33.33% 33.33% 33.33%

C2.22 4 1 0 1 1 1 0 1 0 25.00% 100.00% 100.00% 100.00%

Totals: 20 4 1 2 2 0 0 1 0 33.33% 50.00% 50.00% 50.00%

1. (C2.21 & C2.22) Per Examination Category C-B, Note 4, in the case of multiple vessels of similar design, size, and service, the required examinations may be limited to one vessel or distributed among the vessels.
2. (C2.21) Two welds per item for the Residual Heat Removal Heat Exchanger are exempted from examination with the adoption of ASME Code Case N-706 (ref:

13T-08). The remaining welds in the items are for the four steam generators and are selected for examination under #1 above.

Category C-C Non-Deferred Exams C3.10 2 1 0 0 1 1 0 1 0 50.00% 0.00% 0.00% 0.00%

C3.20 76 8 2 1 4 3 3 5 0 10.53% 12.50% 50.00% 50.00%

C3.30 20 2 0 1 1 1 0 1 0 10.00% 50.00% 50.00% 50.00%

Totals: 98 11 2 2 5 4 3 6 0 11.22% 18.18% 45.45% 45.45%

1. (C3.10) Per Examination Category C-C, Note 4, for multiple vessels of similar design, function, and service, only one welded attachment of only one of the multiple vessels shall be selected for examination. Conservatively, a welded attachment of each type of welded attachment of one of multiple vessels will be examined.
2. (C3.20 & C3.30) Per Examination Category C-C, Note 5, for piping, pumps, and valves, a sample of 10% of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined. This requirement is conservatively interpreted to mean that 10% of the total Class 2 welded attachments shall be examined. The interpretation is consistent with the previous NRC condition on the use of Code Case N-509.

Category C-H Non-Deferred Exams C7.10 49 49 N/A 49 N/A N/A 12 N/A 0 100.00% 100.00% 124.49% 0.00%

Totals: 49 49 N/A 49 WA N/A 12 N/A 0 100.00% 100.00% 124.49% 0.00%

1. (C7.10) "% Completed" exceeds 100% since Class 2 pressure tests are performed each inspection period.
2. (C7.10) Forty-nine components representing the twenty-nine systems/ in Class 2 as reported in the ISI Program Plan.

Section 3.0 Page 6 of 7

(This report is used to verify that the periodic BYRON STATION UNIT 2 - 3RD INTERVAL ASME SECTIO N Xl (The percentage requirements of Tables lWx-requirements of Tables IWx-2412-1 will be met by EXAMINATION STATUS REPORT 2412-1 apply to the Category and were tne interval scnedule.) . applied to each Item only wnen practical.)

  1. of Total # Exams Com pleted  % Exams Comnleted Item No. I Comp Selected Min Per 1 Max Min Per 2 Max Per 3  % Selected Period 1 Period 2 Period 3 Category F-A Non-Deferred Exams F1.10 467 120 20 31 60 29 18 59 0 25.70% 25.83% 40.83% 40.83%

F1.20 659 109 18 25 54 30 23 56 0 16.54% 22.94% 44.04% 44.04%

F1.30 370 41 7 9 20 12 9 21 0 11.08% 21.95% 43.90% 43.90%

F1.40 70 32 6 6 16 10 1 18 0 45.71% 18.75% 21.88% 21.88%

Totals: 1566 302 49 71 151 80 51 155 0 19.28% 23.51% 40.40% 40.40%

1. (F1.40) Per Examination Category F-A, Note 3, for multiple components other than piping within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.
2. (F1l.30 & F1.40) Class 3 components included in table. IWF-2410 completion percentage applies to entire Examination Category.

Category R-A Non-Socket Welds 1 242 61 10 23 30 8 6 22 0 25.21% 37.70% 47.54% 47.54%

2 130 39 7 20 19 0 5 9 0 30.00% 51.28% 64.10% 64.10%

4 1364 140 23 36 70 34 2 69 0 10.26% 25.71% 27.14% 27.14%

5 71 9 2 7 4 -2 0 -1 0 12.68% 77.78% 77.78% 77.78%

Totals: 1807 249 40 86 124 39 13 100 0 13.78% 34.54% 39.76% 39.76%

1. (BER Welds) The # of Comp and # Selected include all BER welds which have been integrated into the RISI Program and are selected in accordance with the Risk Informed BER methodology.

Category R-A Socket Welds 2 84 26 N/A 52 N/A N/A 26 N/A 0 30.95% 200.00% 300.00% 300.00%

4 172 21 N/A 42 N/A N/A 21 N/A 0 12.21% 200.00% 300.00% 300.00%

5 334 32 N/A 64 N/A N/A 32 N/A 0 9.58% 200.00% 300.00% 300.00%

Totals: 590 79 N/A 158 N/A N/A 79 N/A 0 13.39% 200.00% 300.00% 300.00%

1. Socket welds for Examination Category R-A piping structural elements are listed separately from butt welds because socket welds are selected for examination in "each" refueling outage. Including socket welds in the # of Comp, Total Selected, and # Selected fields with the butt welds would misrepresent the %

completed distributions for the remainder of the Examination Category. The "% Completed" exceeds 100% since they are examined each outage per ASME Code Case N-578-1, Table 1, footnote 12.

Section 3.0 Page 7 of 7

SECTION 4.0 7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 1 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Auxiliary Feedwater System (AF)

Compponent or Manufacturer Manufacturer Appurtenance or Installer Serial No. Province No. Board No.

2-AF-2-1 Hunter Corporation N/A N/A N/A 2-AF-2-2 Hunter Corporation N/A N/A N/A Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exel6n.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 2 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Auxiliary Feedwater System (AF)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2FW87BC- Pacific Scientific 12034 NA NA 3/2FW10001S Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used,.provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 3 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Containment Spray System (CS)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2-CS-2-1 Hunter Corporation N/A N/A N/A 2-CS-2-2 Hunter Corporation N/A N/A N/A Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 4 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Containment Spray System (CS)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2CS06AA- HUNTER N/A NA NA 6/2CS06033A Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Compter Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 5 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Containment Spray System (CS)

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

2CS02AA- Pacific Scientific 16636 NA NA 10/2CS03A007S 2 2CS02AB- Pacific Scientific 9178 NA NA 10/2CS03B01 8S Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 6 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Chemical & Volume Control System (CV)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.

Serial No.

2-CV-2-1 Hunter Corporation N/A N/A N/A 2-CV-2-1 0 Hunter Corporation N/A N/A N/A 2-CV-2-2 Hunter Corporation N/A N/A N/A 2-CV-2-3 Hunter Corporation N/A N/A N/A 2-CV-2-4 Hunter Corporation N/A N/A N/A 2-CV-2-5 Hunter Corporation N/A N/A N/A

,2-CV-2-6 Hunter Corporation N/A N/A N/A 2-CV-2-7 Hunter Corporation N/A N/A N/A Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISl Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 7 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Chemical & Volume Control System (CV)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2CV05CB- HUNTER N/A NA NA 6/2CV08007V 2CV09A- HUNTER N/A NA NA 4/2CV01AO64X 2CV45B-2/2CV22007X HUNTER N/A NA NA 2CV45B-2/2CV22008X HUNTER N/A NA NA 2CV45B-2/2CV2201 OX HUNTER N/A NA NA 2CV45B-2/2CV2201 1X HUNTER N/A NA NA 2CV45B-2/2CV22016A HUNTER N/A NA NA 2CVB7A-3/2CV06005X HUNTER N/A NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 8 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Chemical & Volume Control System (CV)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer or InstallerSttorNina Serial No. Province No. Board No.

2CVA3B-2/W-70 Hunter Corp. 2-CV-1-N5 NA NA 2CVA3B-2/W-71 Hunter Corp. 2-CV-1-N5 NA NA 2CVA3B-2/W-72 Hunter Corp. 2-CV-1-N5 NA NA 2CVA3B-2/W-73 Hunter Corp. 2-CV-1-N5 NA NA 2CVA3B-2/W-80 Hunter Corp. 2-CV-1-N5 NA NA 2CVA3B-2/W-81 Hunter Corp. 2-CV-1-N5 NA NA 2CVA5AA-2/W-06 Hunter Corp. 2-CV-1-N5 NA NA 2CVA5AA-2/W-07 Hunter Corp. 2-CV-1-N5 NA NA 2CVA6AA-2!W-04 Hunter Corp. 2-CV-1-N5 NA NA 2CVA6AA-2/W-05 Hunter Corp. 2-CV-1-N5 NA NA 2CVA7AA-2!W-06 Hunter Corp. 2-CV-1-N5 NA NA 2CVA7AA-2/W-07 Hunter Corp. 2-CV-1-N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelen.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 9 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200

.7. Components Inspected: Chemical & Volume Control System (CV)

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

2CVA7AA-2/W-08 Hunter Corp. 2-CV-1-N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exeln.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 10 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Chemical & Volume Control System (CV)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2CV1OB-3/2CV04002S Lisega 01615143/008 NA NA 2CV1OB-3/2CV04012S Lisega 02615163/012 NA NA 2CV1 OCA- Pacific Scientific 7738 NA NA 3/2CV22002S 2CV1 0DB- Pacific Scientific 2184 NA NA 2

3/2CV02009S 2CV1 5AC- Pacific Scientific 23855 NA NA 3/4/2CV29002S 2CVA6AA- Pacific Scientific 4099 NA NA 2

2/2CV09026S 2CVA7AA- Pacific Scientific 8084 NA NA 2

2/2CV25012S 2CVB7BA- Pacific Scientific 1575 NA NA 3/2CV23005S Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7129/2010 Exelin..

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 11 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Fuel Pool Cooling System (FC)

Manufacturer SttorNina Component or Manufacturer or Installer Appurtenance or Installer Serial No. Province No. Board No.

2-FC-2-1 Hunter Corporation N/A N/A N/A Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon-Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 12 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A Z5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Feedwater System (FW)

Manufacturer Component or Manufacturer orMnnstaller State or National Appurtenance or Installer oSerial No. Province No. Board No.

2-FW-2-2 Hunter Corporation N/A N/A N/A Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010

_Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 13 of 53)

1. Owner: Exelon Generation Company, (EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Feedwater System (FW)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.

Serial No.

2FW03DA- HUNTER N/A NA NA 16/2FW02020X 2FW81AA- HUNTER N/A NA NA 6/2AF06038R 2FW81 BA- HUNTER N/A NA NA 6/2AF06040V Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010

  • Exeln.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 14 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Feedwater System (FW)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.

Serial No.

2FW03DA-16/CO1 Hunter Corp. 2-FW-5-N5 NA NA 2FW03DA-1 6/C02 Hunter Corp. 2-FW-5-N5 NA NA 2FW81 BA-6/C07 Hunter Corp. 2-FW-5-N5 NA NA 2FW87CA-6/CO1- Hunter Corp. 2-FW-5-N5 NA NA 2FW87CA-6/C02 Hunter Corp. 2-FW-5-N5 NA NA 2FW87CA-6/C03 Hunter Corp. 2-FW-5-N5 NA NA 2FW87CA-6/C04 Hunter Corp. 2-FW-5-N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 15 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Feedwater System (FW)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2FW03DA- Pacific Scientific 2565 NA NA 16/2FW02012S 2FW03DA- Pacific Scientific 8270 NA NA 2

16/2FW02016S 2FW03DB- Pacific Scientific .4794 NA NA 2

16/2FW03017S 2FW03DD- Pacific Scientific 8201 NA NA 2

16/2FW05022S 2FW87CC- Pacific Scientific 19389 NA NA 2

6/2FW08005S 2FW87CC- Pacific Scientific 20613 NA NA 6/2FW08006S Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 16 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Main Steam System (MS)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2-MS-2-1 Hunter Corporation N/A N/A N/A 2-MS-2-2 Hunter Corporation N/A N/A N/A Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 17 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Main Steam System (MS)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2MS07AA- HUNTER N/A NA NA 28/2MS01 205X 2MS07AC- PACIFIC SCIENTIFIC 13785/113772 NA NA 28/2MS01 101S Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/2912010 Exelkn.

Byron Station Unit 2 B2R15 ISl Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 18 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road; Warrenville, Illinois 60555 (Name and Address of Owner),
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200.
7. Components Inspected: Main Steam System (MS)

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

2MS01 AC- Pacific Scientific 10537 NA NA 32.75/2MS07006-S1 2MS01 AC- Pacific Scientific 10536 NA NA 32.75/2MS07006-S2 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelekn Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 19 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Off Gas System (OG)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.

Serial No.

2-OG-2-1 Hunter Corporation N/A N/A N/A Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon..

Byron Station Unit 2 B2R15 ISl Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 20 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Process Sampling System (PS)

Component or Manufacturer or Installer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2-PS-2-3 Hunter Corporation N/A N/A N/A 2-PS-2-4 Hunter Corporation N/A N/A N/A 2-PS-2-5 Hunter Corporation N/A N/A N/A 2-PS-2-6 Hunter Corporation N/A N/A N/A Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 21 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Pressurizer (PZR)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RY-01-S/PC-05 Westinghouse Corp. 1741 U-201441 W13582 2RY-01 -S/PL-04 Westinghouse Corp. 1741 U-201441 W 13582 2RY-01-S/PN-02 Westinghouse Corp. 1741 U-201441 W13582 2RY-01-S/PN-02-NIR Westinghouse Corp. 1741 U-201441 Wi 3582 2RY-01 -S/PN-03 Westinghouse Corp. 1741 U-201441 W 13582 2RY-01-S/PN-03-NIR Westinghouse Corp. 1741 U-201441 W 13582 2RY-01-S/PN-05-NIR Westinghouse Corp. 1741 U-201441 W13582 2RY-01-S/PN-06 Westinghouse Corp. 1741 U-201441 W13582 2RY-01 -S/PN-06-NIR Westinghouse Corp. 1741 U-201441 W 13582 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, an'd (3) each sheet is numbered and the number of sheets is recorded at the top of this form:

Computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 22 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2-RC-1-1 Hunter Corporation N/A N/A N/A Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exekon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 23 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RC14AB- HUNTER N/A NA NA 2/2CV15016V Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exeln.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 24 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RC01AA-29/J06 Hunter Corp. 2-RC-1-N5 NA NA 2RC-01-R/RPVS-A F1 Westinghouse Corp. 640-0012-51 B-09062 N-200 2RC-01 -R/RPVS-D F1 Westinghouse Corp. 640-0012-51 B-09062 N-200 2RC-01-R/RPVS-E F1 Westinghouse Corp. 640-0012-51 B-09062 N-200 2RC-01 -R/RPVS-F F1 Westinghouse Corp. 640-0012-51 B-09062 N-200 2RC-01 -R/RPVS-H F1 Westinghouse Corp. 640-0012-51 B-09062 N-200 2RC03AA-27.5/JO2A Hunter Corp. 2-RC-1-N5 NA NA 2RC03AA-27.5/J04 Hunter Corp. 2-RC-1 -N5 NA NA 2RC13AA-2/W-01 Hunter Corp. 2-RC-1 -N5 NA NA 2RC13AA-2/W-02 Hunter Corp. 2-RC-1 -N5 NA NA 2RC13AA-2/W-03 Hunter Corp. 2-RC-1-N5 NA NA 2RC13AA-2/W-04 Hunter Corp. 2-RC-1 -N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/2912010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 25 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RC13AA-2/W-05 Hunter Corp. 2-RC-1 -N5 NA NA 2RC13AB-2/W-01 Hunter Corp. 2-RC-1-N5 NA NA 2RC13AC-2/W-01 Hunter Corp. 2-RC-1-N5 NA NA 2RC13AD-2/W-01 Hunter Corp. 2-RC-1-N5 NA NA 2RC14AA-2/W-01 Hunter Corp. 2-RC-1-N5 NA NA 2RC14AA-2/W-01A Hunter Corp. 2-RC-1 -N5 NA NA 2RC14AA-2/W-01B Hunter Corp. 2-RC-1-N5 NA NA 2RC14AA-2/W-01C Hunter Corp. 2-RC-1 -N5 NA NA 2RC14AA-2/W-02 Hunter Corp. 2-RC-1 -N5 NA NA 2RC14AA-2/W-03 Hunter Corp. 2-RC-1-N5 NA NA 2RC14AA-2/W-04 Hunter Corp. 2-RC-1-N5 NA NA 2RC14AA-2/W-05 Hunter Corp. 2-RC-1 -N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 26 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RC14AA-2/W-06 Hunter Corp. 2-RC-1-N5 NA NA 2RC14AA-2/W-07 Hunter Corp. 2-RC-1 -N5 NA NA 2RC14AA-2/W-08 Hunter Corp. 2-RC-1 -N5 NA NA 2RC14AA-2/W-09 Hunter Corp. 2-RC-1-N5 NA NA 2RC14AA-2/W-10 Hunter Corp. 2-RC-1-N5 NA NA 2RC14AA-2/W-11 Hunter Corp. 2-RC-1 -N5 NA NA 2RC16AA-2/W-03 Hunter Corp. 2-RC-1 -N5 NA NA 2RC16AA-2/W-04 Hunter Corp. 2-RC-1 -N5 NA NA 2RC16AA-2/W-05 Hunter Corp. 2-RC-1 -N5 NA NA 2RC16AA-2/W-06 Hunter Corp. 2-RC-1-N5 NA NA 2RC16AA-2/W-07 Hunter Corp. 2-RC-1-N5 NA NA 2RC16AB-2/W-04 Hunter Corp. 2-RC-1 -N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 27 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RC)

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RC16AB-2/W-05 Hunter Corp. 2-RC-1-N5 NA NA 2RC16AC-2/W-08 Hunter Corp. 2-RC-1-N5 NA NA-2RC16AD-2/W-01 Hunter Corp. 2-RC-I.-N5 NA NA 2RC22AA-1.5/W-01 Hunter Corp. 2-RC-1-N5 NA NA 2RC22AA-1 .5/W-O Hunter Corp. 2-RC-1 -N5 NA NA 2RC22AC-1.5/W-01 Hunter Corp. 2-RC-1 -N5 NA NA 2RC22AC-1.5/W-06 Hunter Corp. 2-RC-1 -N5 NA NA 2RC22AD-1.5/W-01 Hunter Corp. 2-RC-1 -N5 NA NA 2RC22AD-1 .5/W-08 Hunter Corp. 2-RC-1 -N5 NA NA 2RC26A-2/W-01 Hunter Corp. 2-RC-1-N5 NA NA 2RC26A-2/W-02 Hunter Corp. 2-RC-1-N5 NA NA 2RC28A-3/Zone 1 Hunter Corp. 2-RC-1 -N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S-REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 28 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RC30AA-1.5/W-01 Hunter Corp. 2-RC-1-N5 NA NA 2RC35AA-6/J02 Hunter Corp. 2-RC-1 -N5 NA NA 2RC35AA-6/J03 Hunter Corp. 2-RC-1 -N5 NA NA 2RC35AA-6/J04 Hunter Corp. 2-RC-1 -N5 NA NA 2RC35AA-6/J05 Hunter Corp. 2-RC-1-N5 NA NA 2RC37A-3/Zone 2 Hunter Corp. 2-RC-1-N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelrn..

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 29 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RC01 BA- Boeing 27 NA NA 2A/2RC01 BA-A 2RC01 BA- Boeing 35 NA NA 2A/2RC01 BA-B 2RC01BB- Boeing 9 NA NA 2B/2RC01 BB-A 2RC01BB- Boeing 15 NA NA 2B/2RC01 BB-B 2RC01 BC- Boeing 19 NA NA 2C/2RC01 BC-A 2RC01 BC- Boeing 7 NA NA 2C/2RC01 BC-B 2RC01BD- Boeing 5 NA NA 2D/2RC01 BD-A 2RC01 BD- Boeing 31 NA NA 2D/2RC01BD-B 2RC08AA- Pacific Scientific 14672 NA NA 3/4/2RC16009S 2RC13AB- Pacific Scientific 8034 NA NA 2/2CV1 5002S 2RC14AD- Pacific Scientific 3105 NA NA 2 2/2CV25019S 2RC14AD- Pacific Scientific 17595 NA NA 2/2CV25020S Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 30 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RC)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RC14AD- Pacific Scientific 8040 NA NA 2/2CV25024S 2 2RC22AA- Pacific Scientific 12848 NA NA 1.5/2RC16001S 2 2RC22AA- Pacific Scientific 2928 NA NA 1.5/2RC16011S 2RC22AB- Pacific Scientific 9917 NA NA 1.5/2RC17015S 2RC48BB- Pacific Scientific 3134 NA NA 1/2/2RC90B008S Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 31 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC),.4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Residual Heat Removal System (RH)

Component or Manufacturer Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

2-RH-2-1 Hunter Corporation N/A N/A N/A 2-RH-2-2 Hunter Corporation N/A N/A N/A 2-RH-2-3 Hunter Corporation N/A. N/A N/A 2-RH-2-6 Hunter Corporation N/A N/A N/A Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 32 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Residual Heat Removal System (RH)

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RH01CA- HUNTER N/A NA N/A 16/2S106259X Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code'Rules (Page 33 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church'Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Residual Heat Removal System (RH)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RH01BA-12/C03 Hunter Corp. 2-RH-2-N5 NA NA 2RH02AA-8/C47 Hunter Corp. 2-RH-2-N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 34 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Residual Heat Removal System (RH)

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RH02AA- Pacific Scientific 12105 NA NA 8/2RH07003S 2RH02AA- Pacific Scientific 15103 NA NA 8/2RH07012S 2RH26AA- Pacific Scientific 8077 NA NA 3/4/2RH02121 S Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010

~Exekrn.

Byron Station Unit'2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 35 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: 'N-200
7. Components Inspected: Reactor Pressure Vessel (RPV)

Component or Manufacturer Manufacturer State or National or Installer SttorNtna Appurtenance or Installer Serial No. Province No. Board No.

2RC-01-R/RPV BMI Westinghouse Corp. 640-0012-51 B-09062 N-200 2RC-01 -R/RPV HEAD Westinghouse Corp. 640-0012-52 B-09062 N-200 PEN 2RC-01 -R/RPV HEAD Westinghouse Corp. 640-0012-52 B-09062 N-200 SURF 2RC-01 -R/RPV Westinghouse Corp. 640-0012-51 B-09062 N-200 INTERIOR Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 36 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RY)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RY03BC-6/FLG 1-12 Hunter Corp. 2-RC-1-N5 NA NA 1 2RY76A-2/FLG 1-8 Hunter Corp. 2-RC-1 -N5 NA NA 1 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn-Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the.ASME Code Rules (Page 37 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RY)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RY-01-S/SKT HUNTER N/A NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 38 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RY)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RY01B-6/J28 Hunter Corp. 2-RC-1 -N5 NA NA 2RY01 B-6/J29 Hunter Corp. 2-RC-1 -N5 NA NA 2RY01B-6/J30 Hunter Corp. 2-RC-1-N5 NA NA 2RY01C-4/J01S Westinghouse Corp. 2-RC-1-N5 NA NA 2RY-01 -S/PN-01 -FlS Westinghouse Corp. 1741 U-201441 W 13582 2RY-01-S/PN-02-F2S Westinghouse Corp. 1741 U-201441 W13582 2RY-01 -S/PN-03-IF3S Westinghouse Corp. 1741 U-201441 W 13582 2RY-01 -S/PN-04-F4S Westinghouse Corp. 1.741 U-201441 W 13582 2RY-01-S/PN-05-F5S Westinghouse Corp. 1741 U-201441 W13582 2RY-01 -S/PN-06-F6S Westinghouse Corp. 1741 U-201441 W 13582 2RY02A-6/JO1 S Westinghouse Corp. 2-RC-1 -N5 NA NA 2RY03AA-6/JO1 S Westinghouse Corp. 2-RC-1 -N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelmn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 39 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RY)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RY03AB-6/JO1 S Westinghouse Corp. 2-RC-1 -N5 NA NA 2RY03AC-6/JO1S Westinghouse Corp. 2-RC-1-N5 NA NA 2RY11A-14/JO1S Hunter Corp. 2-RC-1-N5 NA NA 2RY1 8A-2/W-01 Hunter Corp. 2-RC-1 -N5 NA NA 2RY1 8A-2/W-02 Hunter Corp. 2-RC-1 -N5 NA NA 2RY1 8A-2/W-03 Hunter Corp. 2-RC-1-N5 NA NA 2RY18A-2/W-04 Hunter Corp. 2-RC-1 -N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exekon.

Byron Station Unit 2 B2R15 ISl Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 40 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Reactor Coolant System (RY)

Component or Manufacturer Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RY01 B-6/2RY06025- Pacific Scientific 9655 NA NA S1 2RY01 B-6/2RY06025- Pacific Scientific 9558 NA NA S2 2RY02B-3/2RY09077S Hunter Corp. 23126 NA NA 2RY1 8A-2/2RY06114S Pacific Scientific 4356 NA NA 2

2RY34AB- Pacific Scientific 27591 NA NA 1/2/2RC92002S Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information.

in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

computer Generated Form

7/29/2010 Exelmn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 41 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Steam Generator Blowdown System (SD)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.

Serial No.

2SDO1 CB- Lisega 03615873/010 NA NA 2/2SD01 005S Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/2912010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 42 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Steam Generator (SG)

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RC-01 -BNBLT 1-32 Westinghouse Corp. 2095 U-201435 15 1

Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 IS[ Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 43 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Steam Generator (SG)

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

2RC-01 -BA/DRAIN Westinghouse Corp. 2095 U-201435 15 2RC-01-BB/DRAIN Westinghouse Corp. 2096 U-201436 16 2RC-01 -BC/DRAIN Westinghouse Corp. 2097 U-201437 17 2RC-01-BD/DRAIN Westinghouse Corp. 2098 U-201438 18 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exekln.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 44 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Safety Injection System (SI)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.

Serial No.

2SI08HA-2IFLG 1-8 Hunter Corp. 2-SI-i -N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in:, (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 45 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Safety Injection System (SI)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2-SI-2-1 Hunter Corporation N/A N/A N/A 2-SI-2-2 Hunter Corporation N/A N/A N/A 2-SI-2-3 Hunter Corporation N/A N/A N/A 2-SI-2-4 Hunter Corporation N/A N/A N/A 2-SI-2-5 Hunter Corporation N/A N/A N/A 2-SI-2-6 Hunter Corporation N/A N/A N/A 2-SI-2-7 Hunter Corporation N/A N/A N/A Note (1):'Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 46 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Safety Injection System (SI)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

2SI04B- HUNTER N/A NA NA 12/2RH02109X 2SI04B- HUNTER N/A NA NA 12/2RH021 1OX 2SI04D-8/2RH02020X HUNTER N/A NA NA 2SI05CA-8/2SI01024X 'HUNTER N/A NA NA 2SI05CA-8/2S101040X HUNTER N/A NA NA 2SI06BA- HUNTER N/A NA NA 24/2SI06260X 2SI06BA- HUNTER N/A NA NA 24/2SI06261 X 2SI08FA-3/2SI21014X HUNTER N/A NA NA 2SI08HA-2/2SI25009X HUNTER N/A NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelon.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 47 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Safety Injection System (SI)

Component or Manufacturer Manufacturer 'State or National Appurtenance or Installer Serial No. Province No. Board No.

2SI03DA-2/W-08A Hunter Corp. 2-SI-1-N5 NA NA 2SI04B-12/C02 Hunter Corp. 2-SI-2-N5 NA NA 2SI05BA-8/C02 Hunter Corp. 2-SI-2-N5 NA NA 2SI08HA-2/W-01 H~unter Corp. 2-S1-1-N5 NA NA 2SI08HA-2/W-02 Hunter Corp. 2-S1-1-N5 NA NA 2SI08HA-2/W-03 Hunter Corp. 2-SI-1 -N5 NA NA 2SI08HA-2/W-04 Hunter Corp. 2-S1-1-N5 NA NA 2SI08HA-2/W-05 Hunter Corp. 2-S1-1-N5 NA NA 2SI08HA-2/W-06 Hunter Corp. 2-SI-1-N5 NA NA 2SI08JA-1.5/W-01 Hunter Corp. 2-SI-1-N5 NA NA 2SI08JA-1.5/W-02 Hunter Corp. 2-S1-1-N5 NA NA 2SI08JA-1.5/W-03 Hunter Corp. 2-SI-1-N5 NA NA Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 48 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Safety Injection System (SI)

Manufacturer Component or Manufacturer Mansturer State or National Appurtenance or Installer or Installer Province No. Board No.

Serial No.

2SI08JA-1.5/W-04 Hunter Corp. 2-S1-1-N5 NA NA 2SI08JA-1.5/W-05 Hunter Corp. 2-SI-1-N5 NA NA 2SI08JA-1.5/W-05A Hunter Corp. 2-SI-1 -N5 NA NA 2SI08JA-1.5/W-05B Hunter Corp. 2-S1-1-N5 NA NA 2SI08JA-1.5/W-06 Hunter Corp. 2-SI-1 -N5 NA NA 2SI08JA-1.5/W-07 Hunter Corp. 2-SI-1 -N5 NA NA 2SI08JA-1.5/W-10 Hunter Corp. 2-S1-1-N5 NA NA 2SI08JA-1.5/W-14 Hunter Corp. 2-S1-1-N5 NA NA 2SI08JA-1.5/W-14 Hunter Corp. 2-S1-1-N5 NA NA 2SI108JA-1.5/W-15 Hunter Corp. 2-S1-1-N5 NA NA 2SI18FC-2/W-01.02 Exelon.Corp. 2-SI-1-N5 NA NA 1

2SI18FC-2/W-O1A.Oi Exelon.Corp. 2-SI-1-N5 NA NA 1 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelrn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 49 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Nariie and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Safety Injection System (SI)

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

2SI18FC-2/W-01B.01 Exelon Corp. 2-SI-1-N5 NA NA 1

Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelomn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 50 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Safety Injection System (SI)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.

Serial No.

2SI05DC-6/2SI09014- Pacific Scientific 20565 NA NA

$1 2SI05DC-6/2SI09014- Pacific Scientific 20555 NA NA S2 Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 51 of 53).

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Essential Service Water System (SX)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province No. Board No.

Serial No.

2-SX-2-1 Hunter Corporation N/A N/A N/A 2-SX-2-2 Hunter Corporation N/A N/A N/A Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010 Exelkn.

Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page52 of 53)

1. Owner: Exelon Generation Company,(EGC,LLC), 4300 Winfield Road, Warrenville, Illinois 60555 (Name and Address of Owner)
2. Plant: Byron Nuclear Power Station, 4450 North German Church Road, Byron, Illinois 61010 (Name and Address of Plant)
3. Plant Unit: 2- 4. Owner Certificate Of Authorization (if required): N/A
5. Commercial Service Date: 08/22/87 6. National Board Number for Unit: N-200
7. Components Inspected: Essential Service Water System (SX)

Component or Manufacturer Manufacturer State or National Appurtenance or Installer Serial No. Province No. Board No.

.2SX06CA- HUNTER N/A NA NA 14/2SX06009X 2SX06EC- HUNTER N/A NA NA 10/2SX06023A 2SX07EB- HUNTER N/A NA NA 14/2SX09015X Note (1): Baseline Examination Note (2): Snubber examined as a Component Support Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 of this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Computer Generated Form

7/29/2010Exe n Byron Station Unit 2 B2R15 ISI Outage Report FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As Required by the Provisions of the ASME Code Rules (Page 53 of 53)

(BACK)

8. Examination Dates: 10/24/08 to 05/08/10
9. Inspection Period Identification: First Insoection Period
10. Inspection Interval Identification: Third Inspection Interval
11. Applicable Edition of Section Xl: 2001 Addenda 2003
12. Date / Revision of Inspection Plan: 08/15/09 4
13. Abstract of Examinations and Test. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan.

Refer to the Outage Summary Report and ISI Program Plan

14. Abstract of Results of Examinations and Tests.

Refer to the Outage Summary Report

15. Abstract of Corrective Measures.

Refer to the Outage Summary Report We certify that a) the statements made in this report are correct, b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section XI, and c) corrective measures taken conform to the rules of the ASME Code, Section XI.

Certificate of Authorization No. (ifapplicable): N/A Expiration Date: N/A Date: (. /:2 9 Signed for:Exelon Generation Company By:

CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford CT. have inspected the components described in this Owner's Report during the period 1A/24/0& to as1o81io, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Inspectors Signature Commissions: ILL-1254 Date: f,*e f ,20 National Board, State, Province, and Endorsements Computer Generated Form

SECTION 5.0 DOCUMENT NO.: 2.2 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xi

1. Owner Exelon Nuclear Date 4-26-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of I Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 00488016-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone &Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address
4. Identification of System CHEMICAL &VOLUME CONTROL (CV)
5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S74 Addenda, 1644 Rev. 7, 1651, 1682, 1683,1685, 1686, 1728, 1729, 1734, N-108, N-180 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built Snubber Pacific PSA - 1/4 Scientific 23855 N/A 2CV29002S 1982 Removed YES Snubber, Lisega LISEGA 30900553/008 N/A 2CV29002S 2009 Installed NO 301856 RF1 (CAT ID# 1396543-1)

7. Description of Work REPLACED SNUBBER
8. Test Conducted: Hydrostatic [] Pneumatic E] Nominal Operating Pressure El Exempt El VT-3 Other 0 Pressure _psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 00488016-01 Applicable Manufacturers Data Reports to be attached 9 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed __________ *Date 6__/___, 20 10

( Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have inspeted the components described in this Owner's Report during the period to , , and state that to the best of my knowledge and belief, te- Owner has performedAexaminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property dama. e or a loss of any kind arising from or connected with this inspection.

f Commissions ,'11- -A'f 9 Inspector's Signature National Board, State Province, and Endorsements Date: ,20 10 (Final)

DOCUMENT NO.: 2.2 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-26-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 00488060-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL60481 Expiration Date Not Applicable Address
4. Identification of System REACTOR COOLING (RC)
5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S74 Addenda, 1644 Rev. 7, 1651, 1682, 1683, 1685, 1686, 1728,1729, 1734, N-108, N-180 Code Case (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built Snubber Pacific PSA - 1/2 Scientific 2829 N/A 2RC1601 S. 1980 Removed YES Snubber, Lisega LISEGA 30900553/004 N/A 2RC16011S 2009 Installed NO 301856 RF2 (CAT ID# 1033720-1)

7. Description of Work REPLACED SNUBBER
8. Test Conducted: Hydrostatic r] Pneumatic C] Nominal Operating Pressure C1 Exempt 0]

VT-3 Other Z Prressure psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 00488060-01 Applicable Manufacturer's Data Reports to be attached tC*

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed _ _ _ _ _ _ __ ___Date 1,20 10 r Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT

.of -,artford,CT have ipsp9cted the components described in this Owner's Report during the period to ,and state that to the best of my knowledge and belief, 6

th0e dwner has performed xaminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property dgmage or a loss of any kind arising from or connected with this inspection.

c,46 Ae1' Commissions ,jZ'/,10(5"'1 Inspector's Signature National Board, State Province, and Endorsements Date: 4e*z, 1!f' ,20 10 6-V (Final)

( DOCUMENT NO.: 2.2 I FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-24-10 Name 4300 Winfield Road, Warrenville, IL Sheet I of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 00488066-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not ApFilicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address
4. Identification of System REACTOR COOLING (RC)
5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S74 Addenda, 1644 Rev. 7, 1651, 1682,1683, 1685, 1686, 1728, 1729, 1734, N-108, N-8a0 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section Xl Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built Snubber, Pacific PSA - 1/2 Scientific 9917 N/A 2RC17015S 1981 Removed YES Snubber, Lisega LISEGA 30900553/003 N/A 2RC17015S 2009 Installed NO 301856 RF2 (CAT ID# 1033720-1)

7. Description of Work REPLACED SNUBBER
8. Test Conducted: Hydrostatic 0] Pneumatic C] Nominal Operating Pressure 0l Exempt 01 VT-3 Other 0 Pressure psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 00488066-01 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed ___

rl

,_ _ _ _,.., _ Date L", . 20 10 r o Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Larford, CT have inppe ted the components described in this Owner's Report during the period 4Z'g,/*.-'-- to " , and state that to the best of my knowledge and belief, th(ed wner has perform dd-e/aminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore,, neither the Inspector nor his employer shall be liable in any manner for any personal injury or da;mge or a loss of any kind arising from or connected with this inspection.

9d Commissions &Zi- / ".'4 Inspector's Signature National Board, State Province, and Endorsements Date: a.e4W",, .,20 10 Or (Final)

I

DOCUMENT NO.: 3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 2-6-09 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N.German Church Road, Byron, IL Work Order No. 00553426-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N.German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System CV CHEMICAL AND VOLUME CONTROL
5. (a) Applicable Construction Code ASME Section ill 19 74 Edition, W76 Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity:. 2001 Editloni2003 Addenda (c) Section Xl Code Case(s) N/A
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built BOLT, CLOSURE STOCK K29 2CV01 FB EQUIP. N/A 1978 REMOVED NO BOLT, CLOSURE NOVA MACH. HT# 144C N/A 2CV01FB 2006 INSTALLED NO SA-453 GR. 660 PROD. N/A CI# 1019317-1 206_NSALED N

7. Description of Work REPLACED FILTER COVER BOLTING
8. Test Conducted: Hydrostatic El Pneumatic C Norrtinal Operating Pressure El Exempt 0 Other 0 Pressure _ psi Test Temp. _

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 00553426-01 Applicable Manufacturers Data Reports to be attached Original bolting documentation is not available. Condition entered in the Exelon Corrective Action Program.

IR# 00322037 Component was built in 1978 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed X,?- Z Date 3 20 09 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of farord, CT have i speced the components described in this Owner's Report during the period

'I4-2100 to 4, and state that to the best of my knowledge and belief, D the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or propery damage or a loss of any kind arising from or connected with this inspection.

Q14, ý , .- Commissions . -/ tsq/

f5' Inspector's Signature National Board, State Province, and Endorsements Date: A&OK e 20 09

DOCUMENT NO.: 5.2 REV. NO.: 0 I FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date 4-24-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01042618-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address
4. Identification of System Si - SAFETY INJECTION
5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S74 Addenda, 1644 Rev. 7, 1651, 1682, 1683, 1685, 1686, 1728, 1729, 1734, N-108, N-180 Code Case (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built Snubber, Pacific 20565 N/A 2SI09014S1 1986 Removed YES PSA - 3 Scientific Snubber, Pacific 10581 N/A 2SI09014S1 1982 Installed YES PSA -3 Scientific

7. Description of Work REPLACED SNUBBER
8. Test Conducted: Hydrostatic El Pneumatic E] Nominal Operating Pressure [I Exempt E0 VT-3 Other Z Pressure psi Test Temp.

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 01042618-01 Applicable Manufacturer's Data Reports to be attached 'VIEW CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not ApIlIcable Signed /E e a.,," Date "-// ,20 10

.""... __ Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of .Hafford, CT have inspected the components described in this Owner's Report during the period 4*.7_ to

  • and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property dama e or a loss of any kind arising from or connected with this inspection.

az = ;W Commissions /1Z" -/"/ýy

&ý" Inspector's Signature National Board, State Province, and Endorsements Date: ,gffee /'ý/ ,20 10 (Final)

I

DOCUMENT NO.: 4A REV. NO.: 077 I FORM NIS-2 OWNER'S REPORT FOR REPAIR/IEPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 5-7-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N.German Church Road, Byron, IL Work Order No. 1052501-01 Address Repair Organization. P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N.German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System VO - Primary Containment Purge
5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W73 Addenda, 1682 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Edition/2003 Addenda (c) Section Xl Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built EQUALIZATION VALVE JAMESBURY NC17016-02E N/A 2VO5000A 1975 REMOVED YES EQUALIZATION TRENTEC EQ-2-7M021-4 N/A CAT ID #1420998-1 2008 INSTALLED YES DEVICE TRENTEC __-2-7M021-4 N/A UTC# 0002837371 A I ~ .L I J. I

7. Description of Work REPLACED EQUALIZATION VALVE W/ EQUALIZATION DEVICE PER EC#360246
8. Test Conducted: Hydrostatic [I Pneumatic [] Nominal Operating Pressure El Exempt El VT-3 Other 0 Pressure psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/ in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks 1052501-01 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed X - Date 20 10 v * .*Owner'sDesignee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have ipsp9cted the components described in this Owner's Report during the period

,,IVA/fr - to 4AI700//p , and state that to the best of my knowledge and belief, t&e 6wner has performed eam 'inations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property.darnage or a loss of any kind arising from or connected with this ins ection.

WeCommissions l'l-,/ 1157 R Inspector's Signature National Board, State Province, and Endorsements Date:

  • I4 .. ,20 10

DOCUMENT NO.: 4A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI I Owner Exelon Nuclear Date 5-6-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address

2. Plant Byron Nuclear Power Station Unit 02 Name 4480 N. German Church Road, Byron, IL Work Order No. 1052501-03 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N.German Church Road, Byron, IL Expiration Date Not Applicable Address
4. identification of System VQ - Primary Containment Purge
5. (a) Applicable Construction Code ASME Section Ill 19 71 Edition, W73 Addenda, 1682 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 EditionI2003 Addenda (c) Section Xl Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component EQUALIZATION Manufacturer Serial No. No. Identification Built VALVE JAMESBURY Valve Body S/N: N/A 2VQ5000B 1975 REMOVED YES VALVE NC-0149-03-AA EQUALIZATION TRENTEC EQ-2-7M021-6 N/A CAT 113142099"1 2008 INSTALLED YES DEVICE UTC# 0002817047

7. Description of Work Replaced Equalization Valve W/ Equalization Device per EC# 360246
8. Test Conducted: Hydrostatic [I Pr teumatic 5 Nominal Operating Pressure El Exempt C0 VT-3 Other 0 Pressure psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks 1052501-03 -IF Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed Date 7--Z.. ,20 10 er or ers Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have inspected the components described in this Owner's Report during the period to , , and state that to the best of my knowledge and belief, the Owner has perform&J exarminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or prop or a loss of any kind arising from or connected with this inspection.

Commissions /L '.

41 Inspector's Signature National Board, State Province, and Endorsements Date: -2 A-3 20 10 r" if

DOCUMENT NO.: 4A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xi

1. Owner Exelon Nuclear Date 5-10-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N.German Church Road, Byron, IL Work Order No. 1052501-04 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N.German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System VO - Primary Containment Purge
5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W73 Addenda, 1682 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Editlon/2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped

'Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built EQUALIZATION VALVE JAMESBURY NC17016-O2AL N/A 2VQ5001A 1975 REMOVED YES EQUALIZATION TRENTEC EQ-2-7M021-5 N/A CAT ID #1420998 2008 INSTALLED YES DEVICE UTC# 0002837372 208 NTALD E

7. Description of Work REPLACED EQUALIZATION VALVE W/ EQUALIZATION DEVICE PER EC# 360246
8. Test Conducted: Hydrostatic E] Pr ieumatic E] Nominal Operating Pressure 0- Exempt E0 VT-3 Other 0 Pressure psi Test Temp.

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks 1052501-04 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of AuthoriatloNod Not Applicable Signed C",6 Date 2 20 10 Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartprd, CT have ippcted the components described in this Owner's Report during the period Z'e*w r to , and state that to the best of my knowledge and belief, th6 Oner has performed e~aminatlons and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions /I.2-'an/

Inspector's Signature National Board, State Province, and Endorsements Date: a" , . 20 10

'I

DOCUMENT NO.: 4A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 5-10-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N.German Church Road, Byron, IL Work Order No. 1052501-05 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N.German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System VO - Primary Containment Purge
5. (a) Applicable Construction Code ASME Section 1ii 19 71 Edition, W73 Addenda, 1682 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity:. 2001 Editioni2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built EQUALIZATION VALVE JAMESBURY NC17016-02AD N/A 2VQ5001B 1975 REMOVED YES EQUALIZATION TRENTEC EQ-2-7M021-3 N/A CAT ID#1420998 2008 INSTALLED YES DEVICE TRENTEC EQ-2-7M021-3 N/A UTC# 0002837370 2008 INSTALLED YE

7. Description of Work REPLACE EQUALIZATION VALVE W/ EQUALIZATION DEVICE PER EC# 360246
8. Test Conducted: Hydrostatic C3 Pneumatic E] Nominal Operating Pressure Cl Exempt El VT-3 Other 0 Pressure psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/1/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks 1052501-05 Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed Date 7- &-._ , 20 10

(!+/-eroOwner's Designee, Tite CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartf~ord, CT have inspected the components described in this Owner's Report during the period to, and state that to the best of my knowledge and belief, I

tAOwvnar has performed e'xaminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or properjy damage or a loss of any kind arising from or connected with this inspection.

Commissions //Z -1(_'V Dae Inspetors Signature National Board, State Province, and Endorsements Date: f A. ,20 10 j

DOCUMENT NO.: 13.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date 4-30-10 Name 4300 Winfleld Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N.German Church Road, Byron, IL Work Order No. 01176166-03 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL60481 Expiration Date Not Applicable Address
4. Identification of System PRIMARY CONTAINMENT VENTILATION (VP)
5. (a) Applicable Construction Code ASME Sec. III Piping 19 74 Edition, S75 Addenda, N/A Code Case (a) Applicable Construction Code ASME Sec. III Cooler 19 74 Edition, S76 Addenda, 1695-1 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built HEAD BOLT, 1/2 2VP01AC 13x 4 W, SA449 CARRIER HT# 18474 N/A SX-RH-5 1978 Removed NO 13_x_4___,___44 ___Bolt# 20 &21 HT# 2VP01AC, Screw, Hex, 1/a"x NOVA HT#-RH-5AC US Y06420 N/A 4 1/2", SA1931B7 MACHINE SX-RH-5 Bolt# 20 &21 2008 Installed NO CID# 1396320-1

7. Description of Work INSTALLED NEW WATERBOX HEAD BOLTING
8. Test Conducted: Hydrostatic E] Pneumatic F] Norriinal Operating Pressure C Exempt Z Other 0 Pressure _ _ psi Test Temp.

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

-I

9. Remarks WO# 01177789-01 Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed Date C, 20 10

(! Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have inspected the components described in this Owner's Report during the period to ________ , and state that to the best of my knowledge and belief, t Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions /z-/. j-q'/

Inspector's Signature National Board, State Province, and Endorsements Date: <*d/ (, 20 10 (Final)

I

DOCUMENT NO.: 13.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 5-1-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4480 N.German Church Road, Byron, IL Work Order No. 01177789-01 Address Repair Organization. P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL60481 Expiration Date Not Applicable Address
4. Identification of System PRIMARY CONTAINMENT VENTILATION (VP)
5. (a) Applicable Construction Code ASME Sec. III Piping 19 74 Edition, S75 Addenda, N/A Code Case (a) Applicable Construction Code ASME Sec. III Cooler 19 74 Edition, S76 Addenda, 1695-1 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built HEAD BOLT, 1/2" Cooler S/N# 2VP01AB, x 4 W, SA449 CARRIER 7862 N/A SX-LH-5, 1978 Removed NO Bolt# 7 2VPO1AB, Screw, Hex, 1/2 x NOVA HT# SX-LH-5, 2010 Installed NO 4 /A-, SA193/B7 MACHINE US Y06420 N/A St7 CAT ID# 46596-1

7. Description of Work INSTALLED NEW COOLER HEAD BOLT LEFT BANK
8. Test Conducted: Hydrostatic C0 Pneumatic C] Norriinal Operating Pressure IN Exempt C0 Other C3 Pressure 100 psi Test Temp. 68 OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 01177789-01 Applicable Manufacturer's Data Reports to be attached Bolt acceptable per Technical Evaluation 97-014 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed Date ZZ. ,20 10 CERTIFICATE OF INSERVICE INSPECTION I,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of . H tford, CT have inspected the components described in this Owner's Report during the period to ,and state that to the best of my knowledge and belief, the )wner has performled efxaminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or propertydamage or a loss of any kind arising from or connected with this inspection.

Commissions Arz - ,kFi

. Inspector's Signature National Board, State Province, and Endorsements Date: .,20 10 (Final)

DOCUMENT NO.: 13.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 5-1-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N.German Church Road, Byron, IL Work Order No. 01177789-15 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by ShawlStone & Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address
4. Identification of System PRIMARY CONTAINMENT VENTILATION (VP)
5. (a) Applicable Construction Code ASME Sec. III Piping 19 74 Edition, S75 Addenda, N/A Code Case (a) Applicable Construction Code ASME Sec. III Cooler 19 74 Edition, S76 Addenda, 1695-1 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built 2VP01AB, HEAD BOLT, 2 CARRIER Cooer S/N# N/A SX-RH-5 1978 Removed NO x 4 /", SA449 7865406-1 Bolt# 7, 10, 24, 25, 48, 53, 54, 63 2VP01AB, Screw, Hex, Wx NOVA HT# SX-RH-5 4Scre, HA193IB7 MACHINE US Y06420 N/A Bolt# 7, 10, 24, 2010 Installed NO 25, 48, 53, 54, 63 CID# 46596-1

7. Description of Work INSTALLED NEW COOLER HEAD BOLTING RIGHT BANK
8. Test Conducted: Hydrostatic C0 Pneumatic 0] Nominal Operating Pressure 0 Exempt E0 Other 0 Pressure 100 psi Test Temp. 68 °F Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 01177789-15 ;12U Applicable Manufacturer's Data Reports to be attached Bolt acceptable per Technical Evaluation 97-01.4 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XA.

Type Code Symbol Stamp Not Applicable Certificate of Authorizatio o. Not Applicable Signed _. /Q F Date 7-Z.. , 20 10

(*yr Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of IllInois and employed by HSB CT Al of Ha ord, CT havep spected the components described in this Owner's Report during the period to 71.,01,0 , and state that to the best of my knowledge and belief, the 6wner has perfored examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property d piage or a loss of any kind arising from or connected with this inspection.

Commissions /'1 ./,.i" Inspector's Signature National Board, State Province, and Endorsements Date: , 20 10 (Final

DOCUMENT NO.: 7.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl Owner Exelon Nuclear Date 4/30/10 Name 4300 Wlnfleld Road, Warrenville, IL Sheet 1 of 1 Address

2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01177830-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address
4. Identification of System WO (CHILLED WATER)
5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S76 Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section X1 Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built STUD____Geewo STUD Anderson Greenwood MK#: HG-2 N/A 2WO007B 1979 REMOVED NO STUD Nova Ht# 250832 N/A CAT2WO007B ID # 37096-1 '4 INSTALLED NO NUT Anderson MK#: HG-1 N/A 2WO007B 1979 REMOVED NO Greenwood NUT Nova Ht# 251919 N/A 2WA 007B INSTALLED NO

_________ _________CAT I D # 37033-1 A~~ISALD N

7. Description of Work INSTALLED STUDS AND NUTS
8. Test Conducted: Hydrostatic [I Pn eumatic [j Nominal Operating Pressure El Exempt 59 Other E] Pressure psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks W.O. 01177830-01 Applicable Manutacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed Date .20 10

" - -- Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hlrtfd, CT have isp ted the components described in this Owner's Report during the period

ý411", to , and state that to the best of my knowledge and belief, the Owner has performed eiaminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

61*21.4 Zy' l Commissions Aý r/ -,/W 5 'I"

,0e 1 National Board, State Province, and Endorsements Insectr: Signatur Date: Q&rý/ 20 10 (Final)

(A

DOCUMENT NO.: 6A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date 04/26110 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01177875-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name; Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System CV CHEMICAL AND VOLUME CONTROL
5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity, 2001 Editioni2003 Addenda (c) Section XI Code Case(s) N/A
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built VALVE WELD SEAL984TR KEROTEST ADF6-14 9854 THRU 2CV8480A 1976 Corrected NO WELD____ ______ ______ 9857 ____ _____

7. Description of Work Re-installed seal weld between cover and body
8. Test Conducted: Hydrostatic El Pn eumatic El Nominal Operating Pressure El Exempt 0 Other F1 Pressure __psi Test Temp. _

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 01177875-01 Applicable Manufacturer's Data "

Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable CertificateA Authorization No. Not Applicable Signed (J A A.,4A , g&

'AJ )d /AJDWA3I1-- Date .- 20 10 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have i spected the components described in this Owner's Report during the period to tO .,ýg , and state that to the best of my knowledge and belief,

'h6 Owner has performerd*6xaminations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or--

implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damap or a loss of any kind arising from or connected with this inspection.

___ ,___________Commissions 1Z1-/L.E5(

4 . Inspector's Signature National Board, State Province, and Endorsements Date: .... , . ,20 Wl,#

r ,

DOCUMENT NO.: 3.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 04/14/10 Name 4300 WInfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01177885-01/02 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone &Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL60481 Expiration Date Not Applicable Address
4. Identification of System SI
5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W172 Addenda, Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built VALVE, RELIEF CROSBY VALVE N56902-00-0015 N/A 2SI8856A 1976 Removed YES

_____ _____ & GAGE __ _ _ _ ___ _ _ _ ___ _ _ __ _ _ _ _

VALVE, VALV, RELIEF RLIE CROSBY VALVE N56902-00-0016

& GAGE N590-0-01 N/A CAT 2SI8856A ID 27740-1 1973 1973 Installed

_nstalle YES YES

7. Description of Work REPLACE RELIEF VALE 2SI8856A PER PM PROGRAM
8. Test Conducted: Hydrostatic C] Pneumatic C] Norniinal Operating Pressure 0 Exempt C0 Other C1 Pressure 181 psi Test Temp. 86 OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks 01177885-01/02 Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate ,uthoriz

  • Not Applicable Signed .- ý Date :"-,Q,7 _____,_121" 20 10

_"_"_._OR Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT

ýof HartfTord, CT have insp cted the components described in this Owners Report during the period to ,and state that to the best of my knowledge and belief, tK(eOner has performedlxaminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

  • t-- ---

Commissions AZ - /"y Inspector's Signature 9" *l National Board, State Province, and Endorsements Date: 20**62 '

DOCUMENT NO.: 3.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-25-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name

.4450 N. German Church Road, Byron, IL Work Order No. 01178701-01/02 Address Repair Organization, P.O. No., Job No., etc.

3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not Applicable Name Authorzation No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address
4. Identification of System CV - CHEMICAL VOLUME CONTROL
5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, 1649 Code Case (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components
7. Description of Work REPLACED RELIEF VALVE 2CV8121 PER PM PROGRAM
8. Test Conducted: Hydrostatic [] Pneumatic [] Norr iinai Operating Pressure 0 Exempt [I Other 0 Pressure 49 psi Test Temp. 71 °F Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8'/ in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks 01178701-01/02 Applicable Manufacturer's Data Reports to be attached Valve pre-tested / evaluated on WO# 1178701-02 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authogzation No. Not Applicable Signed Date -. , 20 10 er Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois rand employed by HSB CT of Hartford, CT have inspected the components described in this Owner's Report during the period to , , and state that to the best of my knowledge and belief, the 0*ner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property d-age or a loss of any kind arising from or connected with this inspection.

Commissions /1/z- 1",v C" Inspector's Signature National Board, State Province, and Endorsements Date: . , .Afj,, . ,20 10

DOCUMENT NO.: 3.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-27-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 01 Name 4450 N.German Church Road, Byron, IL Work Order No. 01178705-01/02 Address Repair Oraization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL60481 Expiration Date Not Applicable Address
4. Identification of System CC (COMPONENT COOLING)
5. (a) Applicable Construction Code ASME Section III 19 71 Edition, S/72 Addenda, _Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built RELIEF VALVE CROSBY VALVE 5N2CC9427 1975 Removed YES 2CC9427 & GAGE CO. N56895-00-0009 N/A RELIEF VALVE CROSBY VALVE 2CC9427 2CC9427 & GAGE CO N56895-00-0004 N/A CAT ID 1442884-1 1973 Installed YES

7. Description of Work REPLACE RELIEF VALVE 2CC9427
8. Test Conducted: Hydrostatic [I Praeumatic 0 Nominal Operating Pressure 0 Exempt 0 Other El Pressure 122.5 psi Test Temp. 72 OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO 01178705-01/02 Applicable Manufacturers Data Reports to be attached

- CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Not Applicable Certificate of, uthorization No. Not Applicable Signed .w I "-, a/ AJiL 4 k IQa &2Oq.1A,)M(V .. Date -.,,2 20 10 Ownefor Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have inspected the components described in this Owner's Report during the period

/,c4gggac to 'd,,edA , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property dapmage or a loss of any kind arising from or connected with this inspection.

ed* Commissions /L- ,IJ'*./

Inspector's Signature National Board, State Province, and Endorsements Date: 9 .A f, 20 le (Final)

DOCUMENT NO.: 6A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date 4-29-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01178734-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N.German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System CV CHEMICAL AND VOLUME CONTROL
5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Edition/2003 Addenda (c) Section XI Code Case(s) N/A
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built VALVE WELD SEAL KEROTEST N01 -21 9536 2CV8368C 1976 REMOVED NO VALVE SEAL KEROTEST N01 -21 9536 2CV8368C 1976 INSTALLED NO WELD __ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _

7. Description of Work REMOVE / REWELD VALVE SEAL WELD (COVER TO BODY)
8. Test Conducted: Hydrostatic C] Pneumatic 0] Nominal Operating Pressure 0 Exempt C0 Other E] Pressure 950 psi Test Temp. 110 OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 01178734-01 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed _.- Z Date .- Z- ,20 10 Owner or er's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of H-artrd, CT have sp cted the components described in this Owner's Report during the period to _________ , and state that to the best of my knowledge and belief, the O4ner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damane or a loss of any kind arising from or connected with this inspection.

_________________Commissions //Zt - 'Z5 F Inspector's Signature National Board, State Province, and Endorsements Date: ,20 10

DOCUMENT NO.: 4.2 REV. NO.: 0-_I FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xi

1. Owner Exelon Nuclear Date 4/24/10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 01 Name 4450 N.German Church Road, Byron, IL Work Order No. 01178737-01/02 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone &Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL60481 Expiration Date Not ApplIcable Address
4. Identification of System RY - REACTOR COOLANT
5. (a) Applicable Construction Code ASME Section III 1971 Edition, W72 Addenda, 1501 &1649 Code Case (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section Xl Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built VALVE, RELIEF CROSBY VALVE N56964-00-0111 N/A 2RY801OC 1993 REMOVED YES VALVE, RELIEF CROSBY VALVE N56964-00-0049 N/A Cat 1ID RY8010C 1402762-1 1976 1976 INSTALLED INSTALLED YES YES

7. Description of Work REPLACED RELIEF VALVE PER PM PROGRAM
8. Test Conducted: Hydrostatic C] Pneumatic C] Norminal Operating Pressure 0 Exempt C0 Other El Pressure 2229 psi Test Temp. 651 °F Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks 01178737-01/02 t Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorin ation No. Not Applicable Signed - Date ,20 10 er Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Has ford, CT have in pec ed the components described in this Owner's Report during the period

X sCa' to- 4 ,e , and state that to the best of my knowledge and belief, tKe Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property dargag or a loss of any kind arising from or connected with this inspection.

____*_ _*_*f______Commissions /A',( -

.. Inspectr's Signature National Board, State Province, and Endorsements Date: (df, ,20 10 01-(Final)

DOCUMENT NO.: 2-1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 5-4-10 Name 4300 Wlnfleld Road, Warrenville, IL Sheet 1 of I Address
2. Plant Byron Nuclear Power Station Unit 2 Name 4460 N.German Church Road, Byron, IL Work Order No. 01180527-02 Address- Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4460 N. German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System RC-Reactor Coolant
5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S/75 Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 EdItIonI2003 Addenda (c) Section XI Code Case(s) N/A
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built Studs Bethlehem Heat Code: W-77 on (Qty. 2)3/4"-10, Steel Corp. LIFU N/A 2RC23AB-3/4 1981 Removed No SA 193 Gr.BIB Oriainal Const.

Studs Com Ed UTC Nbr: MJ-77 (Qty. 2)31V-10, 0002039994 WO 9M9e70e43-01 SA 193 Gr. B7 Ht. Code: N/A under DCP to install 1999 Removed No

____ __ _____ support 2RC02009G Studs Nova Machine HT #3001306 MJ-77 on (Qty. 4) 34-i-10, Prod. Trace Code N/A 2RC23AB-3/4" 2009 Installed No SA 193 Gr. B7 .. 3T22 Cat Id#37094-1 Nuts Bethlehem Heat Code: MJ-77 on (Oty. 2) 3/40-I0, Steel Corp. LICJ N/A 2RC23AB-3/4" 1981 Removed No SA 194 Gr.4 Orlginal Const.

Nuts Corn Ed UTC Nbr. MJ-77 (Oty. 2) 3/4-10, 000204623 WO 990070543-01 SA 194 Gr. 2H Ht. Code: JNC N/A under DCP to Install 1999 Removed No

_ support 2RC02009G Nuts Nova Machine HT# 241436 MJ-77 on X (Oty. 4) 314-"-0, Prod. N/A 2RC23AB-3/4" 2008 Installed No SA 194 Gr. 2H _ Cat Id# 1394886-1 1 - - I

7. Description of Work Replaced worn flange bolting.
8. Test Conducted: Hydrostatic [I Pneumatic 0 Nor iinal Operating Pressure [I Exempt ED VT-1 Other 0 Pressure _ _ psi Test Temp. °_OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8k in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 01180527-02 '*N Applicaole Manufacturers 0a5a Repons to De attacned CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed g-- Date 7-/ ,20 10 Owns or Owner's Designee, litle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT Of A~ar2rd, CT havesected the components described in this Owner's Report during the period "yf1AtoaA//v , and state that to the best of my knowledge and belief, 16 Owner has performed xaminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property dama* or a loss of any kind arising from or connected with this inspection.

___ Commissions i/LL40-/

e Inspector's Signature National Board, State Province, and Endorsements Date: -Q g X ,20 10

ýJAI

DOCUMENT NO.: 3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date 01///o Name I f 4300 Winfleld Road, Warrenville, IL Sheet 1 of I Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01180530-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System RC REACTOR COOLANT
5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S75 Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Editlon/2003 Addenda (c) Section Xl Code Case(s) N/A
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built STUD Bethlehem HT# 8087874. 2RC76A 1981 REMOVED NO Steel HT Code LIEK N/A_1981___REMOVEDNO THREADED ROD Nova Machine HT# 75262621 N/A CAT ID# 44337-1 2006 INSTALLED NO Products HT CD 281C N/A 2006 INSALLD N NUT Bethlehem HT# 65589 N/A 2RC76A REMOVED NO Steel HT Code LIBP N/A_1981 NUT Nova Machine HT# Q2280A- t CAT ID# 30520-1 Products N/A 2007 INSTALLED NO

7. Description of Work REPLACE FLANGE STUDS AND NUTS.
8. Test Conducted: Hydrostatic [] Pneumatic [] Nominal Operating Pressure [] Exempt 0" Other C] Pressure psi Test Temp.

Note: Supplemental sheets in form of lists, sketches, or drawingsmay be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 01180530-01 v

~ppiicable manuiacturer s uai 1leporrs to be auacnieu CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Autorization No. Not Applicable Signed z'p 7- " Date &/// ,20 /

F 6"

  • 'C(: Owners Designee, Title .

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hytford, CT have inspcted the components described in this Owner's Report during the period 4// to /n ,dstate that to the best of my knowledge and belief, te 6wner has performed e*aminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions /zz/- .0-ý'

4Inspector's Signature National Board, State Province, and Endorsements Date: 9! // 20 . .

REV. NO.:

ý DOCUMENT NO.: 3.2 REV.NO.: 00 1 F DOCUMENT NO.: 3.2 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date Z-'513O Name 4300 WInfleld Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01199605-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not Appllcable Name Authorization No. Not Applicable 36400 S. Essex Road. Wllmlnaton. IL 60481 Expiration Date Not Applicable Address
4. Identification of System RC
5. (a) Applicable Construction Code ASME Section 1II 19 71 Edition, $72* Addenda, ** Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built Bolt, Primary Ht Code: J940 2RC01BA/MJ149B Manway, 1.875" x Nova Machine Ht#: 2M34637 N/A Bolt # 13 2004 Removed No 7.500(

Bolt, Primary Ht Code: J940 2RCO1BA/MJ149B Manway, 1.875" x Nova Machine Ht#: 2M34637 N/A Bolt # 13 2005 Installed No 7500,"

7. Description of Work Replaced Primary Manway Bolt
8. Test Conducted: Hydrostatic [3 Pn eumatic 0 Nominal Operating Pressure El Exempt 0 Other E] Pressure psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8V2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 01199605-01 Applicable Manufacturer's Data Reports to be attached W74 for NB-2331(D), NB2332(A)(2), NB-4334, 4334.1& 4334.2, NB-4335.1, NB-4335.2, & NB-4335.3 1355, 1493-1, 1484,1528 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed , ,5z1,4zl C ob., Date ,/7 ,20 10 a~mer or Owneres Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Ha!3!ord, CT have ipsp~cted the components described in'this Owner's Report during the period

_'to ., , and state that to the best of my knowledge and belief, tle Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or a loss of any kind arising from or connected with this inspection.

_______________Commissions ae Inspector's Signature

&/. /AX_

National Board, State Province, and Endorsements Date: ( f, /)--o ,,20 10 (Final)

DOCUMENT NO.: 2.2 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 5/1/10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N.German Church Road, Byron, IL Work Order No. 01199606-02 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Westinghouse Electric Co. Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable PO Box 158, Madison, PA 15663 Expiration Date Not ApplIcable Address
4. Identification of System REACTOR COOLANT (RC)
5. (a) Applicable Construction Code ASME Section III 19 71 Edition, S72/W74
  • Addenda, ** Code Case (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built HT# 2RC01BB Mechanical Tube NX3188HK NA S/N 2096 2002 Installed NO Plug Westinghouse Lot 11 Row 7 CAT ID 45093 Col. 7

7. Description of Work INSTALL MECHANICAL TUBE PLUGS IN THE 2B SG.
8. Test Conducted: Hydrostatic (I Pneumatic E] Nominal Operating Pressure [] Ex( 9mpt0 Other El Pr essure n/a psi Test Temp. n/a OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks 01199606-02 _6 Applicable Manufacturer's Data Reports to be attached W74 for NB-2331(D), NB-2332(A)(2), NB-4332, NB-4334, 4334.1& 4332.2, NB-4335, NB-4335.1, NB-4335.2. & NB-4335.3
    • 1355, 1493-1, 1484, 1528, NB-4643 Mechanical tube plugs fabricated to ASME Section III 1989 Edition No Addenda with Code Case N-474-1.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authoriz ti No. Not Applicable Signed _ __ __ __Date (/ ,20 10 Owner or/Swners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT 4.

of laro*rd, CT have in pec: d the components described in this Owners Report during the period

.?//hP to -7./,0 / , and state that to the best of my knowledge and belief, the Oner has perform id exdminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or prperty damage or'ass of any kind arising from or connected with this inspection.

a~zwm;ý01 IelrCommissions Inspector's Signature National Board, State Province, and Endorsements Date: 20 10 (Final)

DOCUMENT NO.: 3.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-29-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N.German Church Road, Byron, IL Work Order No. 01212449-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone &Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address
4. Identification of System MS (MAIN STEAM)
5. (a) Applicable Construction Code ASME Section 1II 19 74 Edition, na Addenda, Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built SAFETY VALVE, 6", DRESSER BU01479 N/A 2MS013C 1978 Removed YES 1500# INDUSTRIES SAFETY 1500# VALVE. 6", !INDUSTRIES DRESSER DA27376 N/A 2MS013C 2009 installed YES

______ _ INDUSTRIE Cat ID 1442243-1 STUD, 1-3/8" TEXAS BOLT TRACE#LR7 N/A 2MS013C 1981 REMOVED NO SA193 B7 HT# 8898128

( STUD, 1-3/8" NOVA TRACE #

SA193 B7 MACHINE E382 N/A 2MS013C 2002 INSTALLED NO HT#13853 CAT ID37106-1 NUT, 1-3/8 TEXAS BOLT TRACE#LRB N/A 2MS013C 1981 REMOVED NO SA194 2H HT# 2D9355 TRACE#

NUT, 1-3/8 NOVA 438C N/A 2MS013C 2007 INSTALLED NO SA194 2H MACHINE HT# CAT ID 1394991 -1 11557520

7. Description of Work REPLACE RELIEF VALVE / REPLACED ONE STUD AND TWO (2) NUTS Test Conducted: Hydrostatic [I Pn eumatic [] Nominal Operating Pressure 0 Exempt El Other El Pressure 949.68 psi Test Temp. 651.78 OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks 01212454-01 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Not Applicable Certificate o uthorizat)on No. Not Applicable Signed !V =.4L(UA. ) /6.I.2 OWi'A&iAA'Y"9- Date ,Ž./ ,20 10 Owner-or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have insp cted the components described in this Owner's Report during the period

.to { , and state that to the best of my knowledge and belief, t~e O3wner has perforrned ex~aminations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or properdarnaj or a loss of any kind arising from or connected with this inspection.

Commissions //1/- l "/54 Inspector's Signature National Board, State Province, and Endorsements Date: *-el ,20 10 (Final)

DOCUMENT NO.: 3.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl Owner Exelon Nuclear Date 4/29/10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address

2. Plant Byron Nuclear Power Station Unit 01 Name 4450 N.German Church Road, Byron, IL Work Order No. 01212462-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone &Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address
4. Identification of System MS (MAIN STEAM)
5. (a) Applicable Construction Code ASME Section III 19 74 Edition, na Addenda, Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section Xl Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built SAFETY VALVE, 6", DRESSER BU01487 N/A 2MS015C 1978 Removed YES 11500# INDUSTRIES SAFETY VALVE, 6", DRESSER 2MS01 5C 11500# INDUSTRIES DA27375 N/A

_____ Cat ID 1442238-1 2009 Installed _____

YES

7. Description of Work REPLACE RELIEF VALVE
8. Test Conducted: Hydrostatic E] Pn eumatic [] Non"iinal Operating Pressure 0 Exempt [I Other [] Pressure 949.68 psi Test Temp. 651.78 OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NOS-2 (Back)

9. Remarks 01212452-01 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of4uthorization No. Not Applicable Signed r -,&J"A e 1A I &.OoefVl/

A' Date A , 20 10 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have ipsppcted the components described in this Owner's Report during the period a 7T/ _ to ,=/ , and state that to the best of my knowledge and belief, Ge wner has performled dS/aminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property dama e or a loss of any kind arising from or connected with this inspection.

Commissions 'z,./,- "/

W, Inspector's Signature National Board, State Province, and Endorsements Date: ,wre //6 1/.20 , 20 XWXO 9j2 A001 (Final)

FORM NVR-1 REPORT OF REPAIR C3 REPLACEMENT Q3 OF NUCLEAR PRESSURE RELIEF DEVICES

1. Work performed by: NWS Technologlee, LLC Purchase Order 0 458731 131 Venture Boulevard, Spartanburg. SC 29306
2. Work performed for Exelon Corporation, Byron Nuclar Station 3/4. Owner - name, address and Identification of nuclear power plant Exelon Corporation, Byron Nuclear Station 4450 N.German Church Road Byron IL61010 A
5. a: Repaired pressure relief device: Main Steam E~afety Valve b: Name of manufacturer Consolidated / Dresser c: Identifying nos.

3707R DA27375 n/a steam 2009 (MMp) (mfWs S"N (NWe (senim) (size) (yr.buiRt) d: Construction Code: ASME Section III 197,4 n/a n/a 2 (nerresed"Wivi/don) (edili ) (addenda) (Cods Cases(s)) (Cod. Class)

6. ASME Code Section Xl applicable for Inservice Inspection: 2001 n/a 2003 (edmon) (&*WW*) (Code Case(s))
7. ASME Code Section Xl used for repairs, replacements: 2001 2003 n/a (addendla) (Code Case(s))

(ed9on)

8. Construction Code used for repairs, replacements: 1974 n/a n/a (edftn) (addenda) (Code Case(s))
9. Design responsibiliftis: n/a
10. Opening pressure: 1205 psig Set-pressure adjustment made at NW'S Technologies, LLC using steam
11. Description of work (Indude name and denrng number o replaoment pars): Disassembled, cleaned, inspected.

(a lapped nozzle & passivated seat area, lapl assen'10180. towullau Vý11 W;WW1 W ai I A --

  • and pre-oxidized the X750 disc, load tested the spring,

ýft @Rai atoo 1Z. RIemarKs: Nvv- I reveler 41 1u-w. Nou *i W ,!

CEATIFICATE OF COMPLIANCE I, Cesar V. Sierra certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section Xl of the ASME Code and the National Board Inspection Code "VRW and "NR" rules.

National Board Certificate of Authorization No. 632 to use the "VR" stamp expires April 3, 2012.

81 to use th "NRO Stam expires April 9,2012.

Napn I Board Certificate of Authorization No.

NWS Technologies, LLC .Manger, CIA Date Repair Organization T I. . " . . . . .

CERTIFICATE OF INSPECTION I, Charles, F. Toegel Jr. holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford, CT have inspected the repair, modification or replacement described In this report on f.A& Zo ip and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section XI of the of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules.

By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described In this reporL Futhernore, neither the undersigned nor my employe" shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connectrm~ h s inspctx S/jhf1 D 1~~ NO 0 462,A, N, INO17 19 ~35-4-5

NWS Work Pirogression & Hold Point Checklist tochnologe I Valve Serial Number DA27375 POo. 458731 NWS Traveler # 10-.3 This block to be signed after Indicating hold points and prior to This traveler has been reviewed and approved for use by: Almflo NWS QA-.C* S~a [f Wa Construction Code: ASME Section: III Edition: 74 Addenda: nra CodeCase: n/a Repair Code: ASME Section: XI Edition: 2001 Addenda: 2003 CedeCase: n/a This traeler has been reviewed aiff approved for use by-This traveler has been reviewed and approved for use by:

NWM (H,.SM ANI - ChadnTol Work Step NMS NM QA NW8 NW Ami QA Witness ANt VItness

_Hold Date/IniL Hold Datedlnlt.

This Is a new valve.

1. Receipt Inspection
2. Full disassembly (NWS-R-3 rev 7)
3. Component inaspect n!_
4. Rea (Section XI) components Exenon Attachment s re / a 7L of/ & LP- I" .'//* 7 , 0
5. Replace (Section Xl components (Exelon Attachment 5 reo'd)

G.Lap and oxidize doe X750 disc (NWYS--2 Revt 0) @

7. Lap and peaelvate nozzle seet (NWS-f.3 Rev 0).

S. Inspect Spring I Load Test Spring

9. Valve assembly
10. Set blowdown rings
11. Steam set-pressure certification testing (NWS-T-62 rev 1)
12. Steam seat thtness test.
13. Tighten compression screw locknut &torque seal '
14. Loclcwire, and seat ring pins and cap illwlZip A#
15. Final Inspection LO~
16. Completion of Form NVR-1 1f)(10

.17. Apply nameplate I___.

This block to be signed after completion of work:

This traveler has been reviewed and accepted by:

N UaN r This traveler has been reviewed and accepted by:

1 irI 5415

NWS Cereificateof Conformance technologiesi of work performed for 131 Venture Boulevard Exelon Spartmnburg,SC 29306 Byron Nuclear Station Ph: 864-587-7001 Purchase Order # 458731 Fx: 864-587-9005 Valve Identification Valve SIN: DA27375 Model Number. 3707R Main Steam Set-Pressure: 1205 Dsic Valve OEM: Dresser NWS Traveler # 10-63 Job Summary This was a new valve which had not been installed at site.

Repair. The valve was repaired under the NWS VR/NR programs. The X750 disc was lapped and oxidized disc prior to reuse. The nozzle seat was passivated after lapping.

The spring was load tested with satisfactory results. Wear areas were cleaned as necessary. All wear areas and contact points were lubricated prior to assembly.

Initial Test* The valve was allowed to thermally stabilize at a holding pressure of -1000 psig. A total of four lifts were done. No adjustments were required. The final two lifts were within the required as-left BYRON acceptance range of +1% of set-pressure.

Final Seat Tightness Testing: Following set-pressure certification, system pressure was maintained at 90%. No moisture was detected on a cold bar placed in the vicinity of the seats.

All work was done by NWS personnel. An NWS test supervisor was present during all testing. An HSB of CT reviewed documentation, witnessed nameplate installation, and completed an NVR-1 form.

The valve was cleaned, sealed and packaged for return shipment.

Set-Pressure Certification Lifts (1193 to 1217 psig)

Lift Date Time Set- Inlet Body Spring Ambient Number Pressure Flange Can (PSIG) (°F) (°F) (°F) (LF) 63-0-3 4/7/10 10:25 1214 443 265 141 124 63-0-4 4/7/10 10:32 1206 442 268 142 123 We certify that all work performed was in compliance with the referenced PO and other correspondence, NWS QA System Manual Rev. 4, NWS VR Program Rev. 7, NWS NR Program Rev. 6, NWS Procedures and the documents referenced therein. All required tests and inspections have been performed and the results accepted. Documentation supporting this Certificate of Conformance is available for review as applicable.

NWS Job Coordinator J1LP.uAlLZAP#- Date: V / ?g /Id T.P.Nederostek - V.P. Operatlons' NWS Quality Date: .gIjfjjQ

- (;I" 1

DOCUMENT NO.: 3.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear IDate 4/29/10 Name 4300 Winfleld Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01212454-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not Ap plicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address
4. Identification of System MS (MAIN STEAM)
5. (a) Applicable Construction Code ASME Section Ill 19 74 Edition, na Addenda, Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section Xi Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built SAFETY VALVE, 6", DRESSER BU01495 N/A 2MS017C 1500# INDUSTRIES 1978 Removed YES SAFETY VALVE, 6", DRESSER 2MS01 7C 1500# ____ INDUSTRIES

____ ___ __ _ BR09609

___ ____ ___N/A___ Cat ID 1439913-1 1977 Installed YES

7. Description of Work -REPLACE RELIEF VALVE
8. Test Conducted: Hydrostatic E] Pn eumatic E] Nominal Operating Pressure 0 Exempt 01 Other 0 Pressure 949.68 psi Test Temp. 651.78 °F Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/ in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks 01212454-01 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed ACtUV, .*C*WL er*4 W/* (100I011YAMLO,- Date 4-P 20 10 Owner'or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have insp cted the components described in this Owner's Report during the period to Yo,, a , and state that to the best of my knowledge and belief, the Owner has perform d 12xaminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

541# ,4' Commissions I//- /,f#"4' Inspector's Signature National Board, State Province, and Endorsements Date: 20 10 (Final)

FORM NVR-1 REPORT OF REPAIR tO REPLACEMENT E3 OF NUCLEAR PRESSURE RELIEF DEVICES

1. Work performed by: NWS Technologies, LLC Purchase OrderS 454204 131 Venture Boulevard, Spartanbura, SC 29306
2. Work performed for Exelon Corporation, Byron Nuclear Station 3/4. Owner - name, address and identification of nuclear power plant Exelon Corporation, Byron Nuclear Station 4450 N. German Church Road Byron, IL61010
5. a: Repaired pressure relief device: Main Steam Safety Valve b: Name of manufacturer Consolidated I Dresser c: Identifying nos.

3707R BRO! 409 n/a steam so 77 ilffdft SM) (NW (siawos) (stze) (Yr.buiU) d: Construction Code: ASME Section III 1974 n/a n/a 2 (naes/dodMsm) (adRkm) (addwna) (Cods Case*(*)) (code Class)

6. ASME Code Section XI applicable for inservice inspection: 2001 2003 r/a (addenda) (Code Case())
7. ASME Code Section Xl used for repairs, replacements: 2001 2003 n/a (edin) (addenda) (Cods Case(s))
8. Construction Code used for repairs, replacements: 1974 n/a n/a (scdfln) (addenda) (Code Case(s))
9. Design responsibilities: n/a
10. Opening pressure: 1176 psig Set-pressure adjustment made at NWS Technologies, LLC using steam
11. Description of work (include nuns and denufvtg numier of mploS*mtns parl): Disassembled, cleaned, inspected, lapped nozzle & passivated seat area, lapped and pre-oxidized the X750 disc, load tested the spring, as55uIIU.

J ~~

%.WuImuI

~ ~ ~ ...- -- d4.himW"Aaf ,.0i

&.a.. 0... aboom

ýU'J @ i 211 U5I I0%. 0 011#0 .6- LnAM 0 4 A-PA Nft nOrM re C laced I

_ CERTIFICATE OF COMPLIANCI I, Cesar V. Sierra certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section Xl of the ASME Code and the National Board Inspection Code "V1R" and "NR" rules.

National Board Certificate of Authorization No. 632 to use the "VR0 stamp expires April 3, 2012.

Natoa rd Certificate of Authorization No. 81 se the N stap expires April 9, 2012.

Rechnologies*eoLIC TManager, QA Dats Repair organizatin Au" Irepnefd"v Tmel CERTiFICATE OF INSPECTION I, Charles F. Toogel Jr. holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford, CT have inspected the repair, modification or replacement described in this report on V ?M/I4 . r'oand state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the of the ASME Code and the National Board Inspection Code "VR and "NR" rules.

By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described in this report. Futhermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or conn is ins

,/ ';A, N.I__O 07 1~3 55

NWS Work Ptrogression & Hold Point Checklist Valve Serw Nume. BROR096 PM. 4411 rev I NWS Traveler 0 1046 This block to be sgned altr Indic,*ng hold points end prior to woo This traele has been reviewed anid approved for use by:  %ý == -- 4 Construction Code: ASME Section: III Edition 74 Addenda: n/a CodeCase: N__

Repair Code: ASME Section: Xl Edition: 2001 Addenda: 250 CodeCase N This bveler has bee reviewed and approved for use by: I I 'L This traveler has been reviewed and approved for use by: &af.-4 vwv/.9,#7d4,j V.1..0 44 1 .-' HS S)ANF-Ch .,r IGW.O", __.-M A

work Step NV, f NV OA NYS NMS ANI Q1A Whies P"I Wtives Hold OatilnIt. Hold DatefLnit.

Valve had been tetied at site. Sent to NWS for refurb and st-eam issur certification.

1. Recelpt Inspein_
2. Full dsassembly (NW A-R-3 rev 7)
3. Component inspection
4. Repair (Sectiont X) components (Exelon Atschmnent 5re.,d) ,
5. Replece (Section XI) components (Exelan Afttamenwt 5 reqd)

.. Lap and oxidize the X750 disc (NWS-I-2 Rev 0)

7. Lap and pmatvalve nozzle seat (NW84-3 Rev 0)

- M

8. Inspect Spring I Load Test Sprng
9. Valve assembly
10. Set blowdown rtngs
11. Steam se-pre,,se certtication tesft (NW.S-T-82 rev 1) __,,//__/
12. Steem seat tightness testl _______
13. Tlighten compression screw locknut & torque seal
14. Lockwre and seal ring pins and cap
15. Final Inspection IS. Completion of Form NVR-110 117. Appl nameplate (IloQual l 4 This block to be signed after completion of work*

This traveler has been reviewed and accepted by: /

This traveler has been reviewed and accepted by:

... M ANIJ, 1 ~ .3~i ~i *<

NWS Certificateof Conformance technologies of work performed for 131 Venture Boulevard Exelon Spartanburg,SC 29308 Byron Nuclear Station Ph: 864-587-7001 Fx: 864"587-9005 Purchase Order # 454204 Valve Identification Valve S/N: BR09609 Model Number 3707R Main Steam Set-Pressure: 1175 "sia Valve OEM: Dresser NWS Traveler # 10-66 Job Summary As-found testing had been done at site.

Repair: The valve was repaired under the NWS VR/NR programs. The X750 disc was lapped and oxidized disc prior to reuse. The nozzle seat was passivated after lapping.

The spring was load tested with satisfactory results. Wear areas were cleaned as necessary. All wear areas and contact points were lubricated prior to assembly.

Initial Test: The valve was allowed to thermally stabilize at a holding pressure of -1000 psig. A total of three lifts were done. No adjustments were required. The final two lifts were within the required as-left BYRON acceptance range of +1% of set-pressure.

Final Seat Tightness Testing: Following set-pressure certification, system pressure was maintained at 90%. No moisture was detected on a cold bar placed in the vicinity of the seats.

All work was done by NWS personnel. An NWS test supervisor was present during all testing. An HSB of CT reviewed documentation, witnessed steam certification testing, nameplate installation, and completed an NVR-1 form.

The valve was cleaned, sealed and packaged for return shipment.

Set-Pressure Certification Lifts (1164 to 1186 psig)

Lift Date Time Set- Inlet Body Spring Ambient Number Pressure Flange Can

_(PSIG) (°FO°F) (OF) (TF) 66-0-21B 4/6/10 12:23 1179 469 248 144 114 66-0-3B 4/6/10 12:28 1 1178 1 469 249 144 114 We certify that all work performed was in compliance with the referenced PO and other correspondence, NWS QA System Manual Rev. 4, NWS VR Program Rev. 7, NWS NR Program Rev. 6, NWS Procedures and the documents referenced therein. All required tests and inspections have been performed and the results accepted. Documentation supporting this Certificate of Conformance is available for review as applicable.

NWS Job Coordinator: Date: q*_/_*_/0 NWS Quality Assurance: Date: 0(/_P_/P 3 1Z :3-

DOCUMENT NO.: 3A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4/26/10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 2 Name 4450 N. German Church Road, Byron, IL Work Order No. 01213643-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N.German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System CV - CHEMICAL VOLUME CONTROL
5. (a) Applicable Construction Code ASME Section 1II 19 71 Edition, S72 Addenda, 1540-1 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Editlor/2003 Addenda (c) Section Xl Code Case(s) None
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built Diaphragm Valve ITT Grinnell 74-1658-25-4 N/A 2CV8399 1976 Removed Yes Valve Bonnet ITT GRINNELL Viv. 74-1658-13-2 N/A Cat 2CV8399 ID#38640-1 1976 Installed Yes

7. Description of Work REMOVED BONNET ASSE MBLY FROM OLD VALVE AND REPLACE WITH NEW BONNET ASSEMBLY (INCLUDING DIAPHRAGM).
8. Test Conducted: Hydrostatic E] Pneumatic [] Norniinal Operating Pressure 0 Exempt El Other E] Pressure 35 psi Test Temp. 148 OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/22 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks Applicable Manufacturer's Data Reports to be attached UTILIZED BONNET ASSEMBLY AND DIAPHRAGM FROM VAVLE (CAT ID# 38640-1)

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of.Huthorization No. Not Applicable Signed (w - WA A , M C o0A /fAJA7O)/Q Date 5"- 17 ,20 10 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois - and employed by HSB CT of Hartford, CT have ins cted the components described in this Owner's Report during the period to ,and state that to the best of my knowledge and belief, tl~eOwner has performed /examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or propertyamagor a loss of any kind arising from or connected with this inspe.Ction.

Signature Commissions /l" - ,,/01 tInspectos Inspectors Signature U - - -

a National Board, State Province, and Endorsements Date: -?f /' f 20 , /,

4F 0191,4lel a--'I-r

DOCUMENT NO.: 6A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4/28/10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 2 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01225344-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System SI Safety Injection
5. (a) Applicable Construction Code - Pipe ASME Sect 1II19 74 Edition, S75 Addenda, N/A Code Case (a) Applicable Construction Code - Valve ASME Sect III 19 74 Edition, S76 Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Edition/2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year.. Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built 2SI881 9C Valve Kerotest US6-24 21,428 CI# 32726-1 1978 Removed Yes Valve Kerotest US7-111 21,453 CI#2SI8819C 32726-1 1978 Installed Yes CONSOLIDATED 2I518FC-2" 2006 Removed NO PIPE SCH.160 POWER SUPPLY HT# 505112 N/A CI# 32352-1 PIPE SCH.160 CONSOLIDATED ,T 2SI18FC-2" POWER SUPPLY HT# 505112 N/A CI# 32352-1 2010 Installed NO COUPLING TIOGA PIPE HT# HRV N/A 2SI18FC326 CI# 39261 -1 2008 Removed NO COUPLING Guyon Alloys, Ht. Code: CJW N/A 2SI18FC-2" 1982 Installed NO Inc. CI# 39261-1 1982 Installed NO ORIFICEORFC Consolidated osfdtd HT# 2082ANEI N/A 2S5118FC-2" 2S1F-" 2008 Removed NO FLANGE Power Supply N CAT# 1230885-1 STANDARD Joliet Valves HT# D2283 N/A 2SI18FC-2" 1984 Installed NO FLANGE Inc. HTID2283 N/A Cat Id# 30443-1 1

7. Description of Work REPLACE VALVE, PIPE &FLANGE (PER EC 375527)

Replace flange bolting and orifice plate on 2SI06MC per EC 375527,

8. Test Conducted: Hydrostatic [I Pneumatic [] Nominal Operating Pressure 0 Exempt [-

Other 0J Pressure 0865/ Q)615 psi Test Temp. 87/ N/A OF (1) Class-2 portion, 0 Class-1 portion Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8'/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 01225344-01 "4 Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed e-i - Date - ,20 10 r Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have inspe ted the components described in this Owner's Report during the period

,, to , and state that to the best of my knowledge and belief, the wner has perfo fminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damrne or a loss of any kind arising from or connected with this inspection.

Q 4.* ' -t~ Commissions _, - _ __

__1"0V

'Y -Inspector's Signature National Board, State Province, and Endorsements Date: / 10

FORM NIS-2 SUPPLEMENTAL SHEET

1. Owner Exelon Nuclear Date 4/28/10 Name 4300 Winfield Road, Warrenville, IL Sheet 2 of 2 Address
2. Plant Byron Nuclear Power Station Unit 2 Name 4450 N. German Church Road, Byron, IL Work Order No. 01225344-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name, Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System CC - Component Cooler
5. (a) Applicable Construction Code: Piping ASME Sect III 19 74 Ed, S/75 Ad, None Code Case Applicable Construction Code: Valve ASME Sect 1II 19 74 Ed, S/76 Ad, None Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacement Components 2001 Ed/2003 Ad (c) Section XI Code Cases used, None.
6. Identification of Components Repaired or Replaced and Replacement Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built Pipe Sch. 160 Guyon Alloys Mk.# 749803 N/A 2SI18FC-2 1982 Removed No MRA # 5962 Orifice Plate Hunter Corp. Ht. # K51292 N/A 2SI06MC 1981 Removed No Orifice Plate Energy Steel Ht # 877945 N/A 2SI06MC 2010 Installed No MIC# T25975 Cat/ld: 1443150-1 Flange Studs Hunter Corp. Mk.# LIEH N/A 2SI06MC 1981 Removed No Qty. 8 (MJ-48A)

Flange Studs Nova Machine HT# 7526262 N/A 2SI06MC 2006 Installed No Oty. 8 Prod. TC# 147F Cat/ID: 44337-1 Flange Nuts Nova Machine Mk. #LISP N/A 2SI06MC Qty. 16 Products (MJ-48A)

Flange Nuts Nova Machine HT# 02280A N/A 2SI06MC Qty. 16 Prod. Cat/Id: 30520-1 (Final)

DOCUMENT NO.: 3-1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-26-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 2 Name 4450 N. German Church Road, Byron, IL Work Order No. 01225561-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System SI - Safety Injection
5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W/72 Addenda, 1553-1 Code Case 1649 (nuts)

(b) Applicable Edition of Section XI Used for Repair/Replacement Activity: 2001 Editlon/2003 Addenda (c) Section XI Code Case(s) None

6. Identification of Components t4. aIIgn ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Comoonent Manufacturer Serial No. No. Identification Built Disc for 6" Swing McWilliams S/N: 2075 W10992 EPN: 2SI8818C 1976 Removed No Check Valve. FORGE CO. HT # 65800 (Valve) ID: 6C88 1976 Removed No Disc for 6" Swing IONICS, INC RP-2000 N/A EPN: 2SI8818C 2001 Installed No Check Valve. ID: 6C88 2001 _nstalled No 9 9 4 9 I

  • 4 I I S I 9 4 4 9 9 4 9 9 1 ~ 9 9 4 9

______________ L I .1. & I .1. 1

7. Description of Work Replaced the check valve disc
8. Test Conducted: Hydrostatic [I Pneumatic 0] Noffinal Operating Pressure 0l Exempt Z Other E0 Pressure n/a psi Test Temp. n/a OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8'/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks Reference WO 01225561-01.

alýý Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of uthorization No. Not Applicable Signed (Aja3/4A C. eMA AIM AXW--l, Date "-lI ,20 /

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois rand employed by HSB CT of Hartford, CT have nspcted the components described in this Owner's Report during the period 607eje to ,and state that to the best of my knowledge and belief, th wner has p examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or propertydajn age or a loss of any kind arising from or connected with this inspection.

Commissions /Zzi - /ab'(

Inspector's Signature National Board, State Province, and Endorsements Date:

  • 20 '

(Final)

I DOCUMENT NO.: 5.2 I FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4/25/10 Name 4300 Wlnfleld Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01232858-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not Ap plicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address
4. Identification of System SI - SAFETY INJECTION
5. (a) Applicable Construction Code ASME Section 1II 19 74 Edition, S75 Addenda, NONE Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section Xl Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built BONNET NUT VITCO N2 N/A 2SI8816D 1978 Removed NO HT# 532670 BONNET NUT NOVA MACHINE PRODUCTS TRACE# E578 N/A CAT2SI8816D ID 37057-1 2002 Installed NO 4 4. 4 4 4 4 4.

4 4. 4 .4 4 .4 4.

4 4. 4 4 4 4 4.

4 4. 4 .4 4 .4 4.

7. Description of Work REPLACE DAMAGED BONNET NUT
8. Test Conducted: Hydrostatic C] Pn eumatic C] Nominal Operating Pressure 51 Exempt [

Other E5 Pressure psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 812 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks Replacement per WO 01232858-01 Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed Date 6 - 20 10 OnrsDesignee, Tite CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have inspe ted the components described in this Owner's Report during the period to ,and state that to the best of my knowledge and belief, thfe cfwner has performed efaminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_____ ____ ____ ___Commissions el -/1-445 Inspector's Signature National Board, State Province, and Endorsements Date: 7 ,&20 10

DOCUMENT NO.: 5.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-27-10 Name 4300 WInfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 01 Name 4450 N.German Church Road, Byron, IL Work Order No. 01241053-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone &Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL60481 Expiration Date Not Applicable Address
4. Identification of System SI - Safety Injection
5. (a) Applicable Construction Code ASME Section II1 19 74 Edition, S75 Addenda, None Code Case (b) Applicable Edition of Section Xl Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built PIPE, 2" SCH 160 SANDVIK INC. HT# 745223 N/A 2SI18EB-2" 1977 Removed NO ALLOY ELBOW, 90", 6000# STAINLESS MK# P1 N/A 2SI18EB-2" 1977 Removed NO PRODUCTS HT# 74188 PIPE, 2" SCH 160 CONSOLIDATED HT# 505112N N/A 2SI18EB-2O POWER Cat ID 32352-1 ELBOW, 90°, 6000# ALLOY STAINLESS TRACE#

A91 -00363PJ N/A 1977 INSTALLED NO Cat ID 26875-1 COUPLING, 2", 6000# AMCO FITTINGS HT# EEX N/A 2SI18EB-2" INSTALLED NO CO. Cat ID 26943-1

7. Description of Work INSTALLED PIPING (APPROX. 7 FT.) AND FITTINGS (2 ELBOWS & 1 COUPLING)
8. Test Conducted: Hydrostatic [] Prieumatic [] Nominal Operating Pressure Z Exempt El Other E] Pressure 865 psi Test Temp. 87 OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks 01241053-01.

Applicable Manufacturer's Data Reports to be attached 14 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed " Date - Z ,20 10 Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have 17pcted the components described in this Owner's Report during the period

.Y// 7 to I,"r I , and state that to the best of my knowledge and belief, I the 0rner has perform~d examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property dacnap or a loss of any kind arising from or connected with this inspection.

............... l Commissions '/1/. - /I1W Inspector's Signature National Board, State Province, and Endorsements Date: , 20 10 (Final)

DOCUMENT NO.: 5.1 REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date 4-27-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 01 Name 4450 N. German Church Road, Byron, IL Work Order No. 01241053-08 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not Applicable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address
4. Identification of System Si (SAFETY INJECTION)
5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S75 Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built STRAP, GUIDE WEPIPE HUNTER N/A N/A 2SI17038X 1984 Installed NO GUIDE WELDS

7. Description of Work MODIFIED PIPE SUPPORT 2SI17038X PER EC# 375526
8. Test Conducted: Hydrostatic E] Pneumatic [] Nominal Operating Pressure [I Exempt (]

VT-3 Other Z Pressure psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks 01241053-08 Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authori*To No. Not Applicable Signed Date 20 10

&r~rOwneres Designee, Tidle CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have ins7ected the components described in this Owners Report during the period to , and state that to the best of my knowledge and belief, the-'wner has performed/examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions /Zz Inspector's Signature National Board, State Province, and Endorsements Date: . . ,20 10

DOCUMENT NO.: 4A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI 1 Owner Exelon Nuclear Date 5-2-10 Name 4300 Winfleld Road, Warrenville, IL Sheet 1 of 2 Address

2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N.German Church Road, Byron, IL Work Order No. 01279020-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System RC REACTOR COOLANT
5. (a) Applicable Construction Code - Valves Sect. III 19 74 Edition, S76 Addenda, N-141(1 3) Code Case (a) Applicable Construction Code - Pipe Sect-. IU 19 74 Edition, S75 Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity. 2001 Editlon/2003 Addenda (c) Section XI Code Case(s) N/A
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built PIPE 1/2" SCHED. 10 Unidentified HT# 462521 N/A 2RC31DB 1992 REMOVED NO PIPE 1/2' Consolidated HT #8207J N/A 2RC31 B & 2 I SCHED.160 Power Supply 2RC31C 2000 INSTALLED NO TEE Unidentified HT# KR N/A 2RC31B 2RC31 EA& 1992 1992 REMOVED REMOED_ NO N

TEE Consolidated Power Supply Lot#44050 N/A 2RC31B 2RC31C& 2010 INSTALLED NO ELBOW Unidentified HT Code #PP N/A 2RC31B 1992 REMOVED NO ELBOW Guyon Alloys HT Code# PP N/A 2RC31B 1982 INSTALLED NO Inc. NO

7. Description of Work REPLACED REACTOR HEAD VENT VALVES AND PIPING, REPLACED U-BOLT &

REMOVED / REINSTALLED PIPE SUPPORT WELDS

8. Test Conducted: Hydrostatic [- Pr eumatlc C] Non'ninal Operating Pressure 0 Exempt [I VT-3 Other C] Pressure 2244 psi Test Temp. 557 OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1h in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 01279020-01 Applicable Manufacturer's Data Reports to be attached CAT ID#41641-1 consists of 2 Solenoid Valves, 2 reducers, 2(1/2") nipples, 1(1")

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed ______Date 2-- ,20 10 Q~or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have inspected the components described in this Owner's Report during the period to 74,,, ... ,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property dAmage or a loss of any kind arising from or connected with this inspection.

ele-ý-Ae Commissions //ZI- AfS.

Inspector's Signature National Board, State Province, and Endorsements Date: , ,20 10 t44

FORM NIS-2 SUPPLEMENTAL SHEET

1. Owner Exelon Nuclear Date 5-2-10 Name 4300 Winfield Road, Warrenville, IL Sheet 2 of 2 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01279020-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System RC REACTOR COOLANT
5. (a) Applicable Construction Code - Valves Sect IlI 19 74 Edition, S76 Addenda, N-141(1773) Code Case (a) Applicable Construction Code - Pipe Sect. III 19 74 Edition, S75 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacement Components 2001 Ed/2003 Ad (c) Section Xl Code Cases used, N/A
6. Identification of Components Repaired or Replaced and Replacement Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built SOLENOID VALCOR S/N# 44 N/A 2RC014A 1992 REMOVED YES VALVE ENGINEERING 4 SOLENOID VALCOR S/N# 45 N/A 2RC014C 1992 REMOVED YES VALVE ENGINEERING SOLENOID VALCOR S/N# 42 N/A 2RC014B 1992 REMOVED YES VALVE ENGINEERING SOLENOID VALCOR S/N# 52 N/A 2RC014D 1997 REMOVED YES VALVE ENGINEERING SOLENOID VALCOR VLV ASSY SN# 4 2RC014A & C VALVE ENGINEERING 2RC014A SN# 7 N/A UTC #2837690 2009 INSTALLED YES WELDED ASSY 2RC014C SN# 8 CAT# 41641-1 SOLENOID VALCOR VLV ASSY SN# 3 2RC014B & D VALVE ENGINEERING 2RC014B SN# 5 N/A UTC #2039040 1998 INSTALLED YES WELDED ASSY 2RC014D SN# 6 CAT# 41641-1 __

INSERT 1 X 1/2" Unidentified 4C3414 N/A 2RC014A 1992 REMOVED NO U-BOLT Unidentified HT# 8868763 N/A 2RC99012X 1992 REMOVED NO U-BOLT BERGEN - N/A N/A 2RC99012X 2007 INSTALLED NO POWER CAT# 42291-1 PIPE SUPPORT Exelon N/A N/A 2RC99013X STRAP WELDS 1998 REMOVED NO PIPE SUPPORT Exelon N/A N/A 2RC99013X STRAP WELDS ___2010 INSTALLED NQ PIPE SUPPORT Exelon N/A N/A 2RC99014X STRAP WELDS 1 1_99__I REMOVED NQ PIPE SUPPORT Exelon N/A N/A 2RC99014X STRAP WELDS _____N/A _ N/ 2I10 INSTALLED NO (Final)

I DOCUMENT NO.: 5.2 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 4-25-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01329864-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Shaw/Stone & Webster Type Code Symbol Stamp Not Ap pilcable Name Authorization No. Not Applicable 36400 S. Essex Road, Wilmington, IL 60481 Expiration Date Not Applicable Address
4. Identification of System PRIMARY CONTAINMENT ISOLATION
5. (a) Applicable Construction Code - Weld ASME Sect III 19 74 Edition, S75 Addenda, Code Case
5. (a) Applicable Construction Code - Penn ASME Sect III 197.*4 Edition, S76 Addenda, Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built Penetration# Energy Products 802165-5C N/A 2PC066M 1978 Corrected No Group

7. Description of Work METAL REMOVAL OF A DEFECT PER EC# 379830
8. Test Conducted: Hydrostatic [] Pn eumatic E3 Nominal Operating Pressure C Exempt 0 Other 0 Pressure psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIIS-2 (Back)

9. Remarks WO# 01329864-01 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed C -/t ,Date 20 10 One) or Owneves Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois rand employed by HSB CT of Hartford, CT have ispeted the components described in this Owner's Report during the period

,.to ____/// _ , and state that to the best of my knowledge and belief,

'3 the OWner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section X1.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damae or a loss of any kind arising from or connected with this inspection.

Commissions /Z1%- ,5;604 Aý Inspector's Signature National Board, State Province, and Endorsements Date: al  ! //20 10 (Final) 41

DOCUMENT NO.: 2A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xl

1. Owner Exelon Nuclear Date 5/3/10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4480 N.German Church Road, Byron, IL Work Order No. 1332152-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System RC - REACTOR VESSEL
5. (a) Applicable Construction Code ASME Section III 19 71 Edition, Sf73 Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity. 2001 Edltlon/2003 Addenda (c) Section Xl Code Case(s)
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built Reactor Closure McINNES HT#214444 N/A 2RC01R 1975 CORRECTED NO Stud #11 STEEL HT#214444 N/A 2R0R_7 CORRETED_ N

7. Description of Work MODIFY/TRIM REACTOR VESSEL CLOSURE STUD (HEAD STUD #11) I APPROXIMATELY 5' PER EC 379850
8. Test Conducted: Hydrostatic 0] Pn eumatic 0 Nominal Operating Pressure C0 Exempt 10 Other 0 Pressure psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81h in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO#1332152-01 Appucabie manuracturers Data Reports to be auacnea CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Not Applicable Certificate ot.uthorization No. Not Applicable Signed IJAAIA (a-. Ia 1 , im uWA4/RA)A1'r' Date = - 21, 20 10 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Hartford, CT have inspected the components described in this Owner's Report during the period 4-3p-MO to a. .3,P. O' , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damrage or a loss of any kind arising from or connected with this inspection.

____Commissions __Z__-_J._ __/

Inspector's Signature National Board, State Province, and Endorsements Date: 140' 20 1P JIF (Final

DOCUMENT NO.: 2A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xi

1. Owner Exelon Nuclear Date 5-5-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01335437-08 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL 61010 Expiration Date Not Applicable Address
4. Identification of System (RC) Reactor coolant
5. (a) Applicable Construction Code ASME Section III 19 74 Edition, S76 Addenda, Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section Xl Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built Snubber Control ITT Grinnell Snubber N/A 2RC01 BC-A 1979 Removed NO Valve Assy (BOEING) S/N: 19 Snubber S/N: 19 Snubber Control ITT Grinnell Snubber N/A.Cat id:17296 Valve Assy (BOEING) S/N: 4 UTC# 2038032

7. Description of Work REPLACED SNUBBER CONTROL VALVE ASSEMBLY
8. Test Conducted: Hydrostatic 0- Pn eumatic C Norr iinal Operating Pressure [I Exempt [I VT-3 Other Z Pressure psi Test Temp. °_OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 01335437-08 Applicable Manufacturers Data Reports to be attached CONTROL VALVE ASSEMBLY TESTED ON WO# 1216985-01 CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authoriation No. Not Applicable Signed If - Date C;-Z- ,20 10 CtO er's Designee, "Tits CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois rand employed by HSB CT of Hartford, CT have inspeced the components described in this Owner's Report during the period 4.ýý - to _____,__ , and state that to the best of my knowledge and belief, tKe 6wner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damjge or a loss of any kind arising from or connected with this inspection.

__*_ _*._*__ Commissions 111- jj.4"/

Inspector's Signature National Board, State Province, and Endorsements Date: , ,tf ,g 10

,20

  1. I -

(Final)

DOCUMENT NO.: 4A REV. NO.: 0 FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section Xi

1. Owner Exelon Nuclear Date 5-6-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL Work Order No. 01335438-01 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Byron Mechanical Type Code Symbol Stamp Not Applicable Maintenance Name Authorization No. Not Applicable 4450 N. German Church Road, Byron, IL Expiration Date Not Applicable Address
4. Identification of System RC REACTOR COOLANT
5. (a) Applicable Construction Code ASME Section III 1974 Edition, Sf75 Addenda, 1644-4 Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity. 2001 Edition/2003 Addenda (c) Section XI Code Case(s) N/A
6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

WELDED STUDS Teledyne Melt No. N/A 2RC01BC 1978 REMOVED NO Brown Eng. D5896 H-SG-109 THREADED Nova Machine HT# 230113 N/A CAT ID# 24979-1 2007 INSTALLED NO STUD (4) Prod. HT_2013_/ C I24 - 07 NTL ___NO NUTS Unidentified SA-194 Gr. 2H N/A H-SG-109 2RCOIBC 188 1988 RMVD REMOVED N NO NUTS (12) NovaProd.

Machine HT# 361170 N/A _ ___

CAT ID#37027-1 2007 _ __

INSTALLED -

NO _ _

SLOTTED PLATE Unidentified Unidentified N/A 2RC01BC H-SG-109 1988 CORRECTED NO

7. Description of Work ALTERED SHIM PLATE AND INSTALLED BOLTS AND NUTS ON THE 2C STEAM GENERATOR UPPER LATERAL RESTRAINT, SOUTH EAST SHIM PACK PER EC# 380019
8. Test Conducted: Hydrostatic [] Pneumatic 0 Nominal Operating Pressure 0 Exempt 0l VT-3 Other 0 PressuJre psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 811/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks WO# 01335438-01 41 Appiicaoie manufacturers Data Heporrs to De attacnea CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authori tion N Not AppIlcable Signed Date 20 10

--(!ý r Owner's Desk-tee, Tiffs CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by HSB CT of Haord CT have inspected the components described in this Owner's Report during the period to .4 , and state that to the best of my knowledge and belief, Obwner has performred "examinationsand taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this.Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_________ _________Commissions ii ~

Inspector's Signature National Board, State Province, and Endorsements Date: * ,20 10

/4

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 3-17-10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL P.O. 00451499 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by NWS Technologlea, LLC Type Code Symbol Stamp NR/ VR 131 Venture Boulevard Authorization No. 81/632 Spartanburg, SC 29306 Expiration Date 4-9-12 / 4-3-12 Address
4. Identification of System REACTOR COOLANT (RY)
5. (a) Applicable Construction Code ASME Section III 19 71 Edition, W72 Addenda, None Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition / 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Comoonent Manufacturer Serial No. 4 No. 4.

Identification I Built 4 1 4.

PRESSURIZER CAT ID#

NOZZLE TYPE Crosby Valve VALVE S/N:

RELIEF VALVE & Gage Co. N56964-00-0049 N/A 1402762-1 1976 CORRECTED YES (NOZZLE) UTC# 2705394

7. Description of Work VENDOR - MACHINED NOZZLE TO RETORE SEAT STEP & TOP OF FLANGE TO TOP OF SEAT DIMENSION.
8. Test Conducted: Hydrostatic [I Pneumatic C] Nominal Operating Pressure 0] Exempt 0 Other El Pressure psi Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks P.O. 00451499 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp Not Applicable Certificate of Authorizatio No. Not Applicable Signed l Date 3-/' ,20 10 Owner's Designee, Tide CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by of H rtford, CT have*sp ed the components described in this Owner's Report during the period HSB CT 9

47o t4o ,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions ,/Ze- 141e-Inspector's Signature National Board, State Province, and Endorsements Date:  % f'00'f6' , 20 10 (Final)

FORM NVR-1 REPORT OF REPAIR IM REPLACEMENT 03 OF NUCLEAR PRESSURE RELIEF DEVICES 1.work performed by: NWS Technologies, LLC Purchase Order# 451499 131 Venture Boulevard, Spartanburg, SC 29306

2. Work performed for Exelon Corporation, Byron Nuclear Station 3/4. Owner - name, address and identification of nuclear power plant Exelon Corporation, Byron Nuclear Station 4450 N. German Church Road Byron, IL61010
5. a: Repaired pressure relief device: Pressurizer Safety Valve b: Name of manufacturer: Crosby Valve & Gage Co.

c: Identifying nos.

HB-86-BP N56964-000004 n/a steam 6" 1976 (type) (Wt's S/N) (NB#) (suVice) (size) (yr.built) d: Construction Code: ASME Section III 1971 W72 n/a 1 (namne/section/dslon) (edition) (addends) (Code Caes(s)) (Code Class)

6. ASME Code Section XI applicable for Inservice Inspection: 2001 2003 r/a (edmion) (addenda) (Code Case(s))
7. ASME Code Section Xl used for repairs, replacements: 2001 2003 n/a (edition) (addends) (Code Case(s))
8. Construction Code used for repairs, replacements: 1971 W72 n/a (edition) (addenda) (Code Case(s))
9. Design responsibilities: n/a
10. Opening pressure: 2460 psig Set-pressure adjustment made at NWS Technologies, LLC using steam
11. Description of work incude name and Identifying number of replacement pafts): As-found tested (CEAR 09-49),

disassembled, inspected, cleaned, machined nozzle to restore seat step (CEAR 10-25), lapped seats, checked nozzle torque, lubricated, assembled. Certified set-pressureusing steam. Jacked and lapped to restore seat integrity. Final seat tightness and bellows/gasket integrity verified using gaseous nitrogen.

12. Remarks: NWS Traveler # 09-280. No parts were replaced.

CERTIFICATE OF COMPLIANCE I, Cesar V. Sierra -certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.

National Board Certificate of Authorization No. 632 to use the "VR" stamp expires April 3, 2012.

Natal Board Certificate of Authorization No. 81 tu, the "N stai I April 9, 2012.

I Date Repair Organization repmentatveoAMa Tite CERTIFICATE OF INSPECTION I, Charles F. Toegel Jr. holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of North Carolina and employed by Hartford Steam Boiler of CT of Hartford, CT have inspected the repair, modification or replacement described in this report on 1?AfMZO1o and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.

By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning this repair, modification or replacement described in this report. Futhermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected th ins ""

NoB#1A(r Uo.) 073 I Dat6 =WT110q~~~n";!r"9m 'J 7 cormmssi4pl~ioldtindren4P) uid~&n.

9 i~~~h4~ M~,/ 6L

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Nuclear Date 3-11 -10 Name 4300 Winfield Road, Warrenville, IL Sheet 1 of 1 Address
2. Plant Byron Nuclear Power Station Unit 02 Name 4450 N. German Church Road, Byron, IL P.O. 00454346 Address Repair Organization, P.O. No., Job No., etc.
3. Work Performed by Trentec Type Code Symbol Stamp NPT 4600 East Tech Drive Authorization No. N-2934 Cincinnati, Ohio 45245 Expiration Date 4-9-10 Address
4. Identification of System Primary Containment Purge (VO)
5. (a) Applicable Construction Code ASME Section III 1971 Edition, W73Addenda, None Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 2001 Edition I 2003 Addenda (c) Section XI Code Case(s) NONE
6. Identification of Components ASME Corrected, Code National Removed, or Stamped Name of Name of Manufacturer Board Other Year Installed (Yes or No)

Component Manufacturer Serial No. No. Identification Built EQUALIZING VALVE CAT ID#

DEVICE TRENTIC HT# 736368 N/A 1420998-1 2008 REMOVED NO (PIVOT SHAFT) LOT# 50132266 UTC#

PN: 7M021-100-7 0002817047 EQUALIZING VALVE CAT ID#

DEVICE TRENTIC HT# 736366 N/A 1420998-1 2010 INSTALLED NO (PIVOT SHAFT) LOT# 50193578 UTC#

PN" 7M021-1f00-7 0002817047 EQUALIZING VALVE CAT ID#

DEVICE NOVA HT# 533740 N/A 1420998-1 2008 REMOVED NO (HEX HEAD BOLT) LOT# 50150355 UTC#

PN: 7M021-100-Q9 Q002917047 EQUALIZING VALVE CAT ID#

DEVICE NOVA HT# CR533740 N/A 1420998-1 2010 INSTALLED NO (HEX HEAD BOLT) LOT# 50194461 UTC#

PN_ 7M__ 1-10 n-000o2517047 EQUALIZING VALVE CAT ID#

DEVICE NOVA HT# Q9641 N/A 1420998-1 2008 REMOVED NO (HEX NUT) LOT# 50150348 UTC#

PN6 7M021-100-31 000__817 47 EQUALIZING VALVE CAT ID#

DEVICE NOVA HT# 990200 N/A 1420998-1 2010 INSTALLED NO (HEX NUT) LOT# 50150357 UTC#

PNe 7MO21-100-31 I I 000I2817047

7. Description of Work VENDOR REPLACED PIVOT SHAFT AND BOLTING ON EQUALIZING DEVICE EQUALIZING DEVICE SIN: EQ-2-7M021-6
8. Test Conducted: Hydrostatic [I Pneumatic [D Nonmlinal Operating Pressure [I Exempt [I Other E] Pressure 55.06 psi Test Temp. 75 OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/ in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

FORM NIS-2 (Back)

9. Remarks P.O. 00454346 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and this conforms to the requirements of the ASME Code, Section XI.

Type Code Symbol Stamp Not Applicable Certificate of Authorization No. Not Applicable Signed _r__ ,_ __ _ __ __ __ _" /_ _ _ __-- Date , - 7 ,20 10

( 1ý9)Ownses Designee, Tid CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of lilinols and employed by HSB CT of Hartford, CT have inspected the components described in this Owner's Report during the period

/gly/7n/*,* to 1114Z,/Z , and state that to the best of my knowledge and belief, ttfe O(vner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property d~amae or a loss of any kind arising from or connected with this inspection.

q _. 4 .0 Commissions Iw - I.'9

-inspector's Signature National Board, State Province, and Endorsements Date:  ;,Iý / ,20 10 (Final)

ER-AA-330-009 Revision 5 Page 33 of 39 ATTACHMENT 5 Repair Specification Page 1 of 2 Purchase Order 00454346 P.O. Rev O Date 12-14-09 Repair Organization Trentec The following requirements shall be completed or imposed for the procurement of a "Repair Organization' performing ASME Section XI Repairs/Replacements to ASME components.

1) Description of Work P.O. Rev 0 Vendor to refurbish egualizlna device (S/N - EQ-2-7M021-6).

(CAT ID# 1420998-1). UTC# 2817047.

Replace Pivot Shaft (Dwa. No. 7M021-100) Piece No. 7)

2) Applicable Repair Code Construction Code: ASME Section II11 Class-MC, Subsection NE, 1971 Edition / Winter of 1973 Addenda Repair I Replacement Code: ASME Section XI1 Class-MC. 2001 Edition 12003 Addenda
3) Program Requirements E] Work shall be performed in accordance with an 'N* Certificate Program reviewed and accepted by Exelon Nuclear Assessment.

El Work shall be performed in accordance with a National Board "NR" Certificate Program reviewed and accepted by Exelon Nuclear Assessment.

[] Work shall be performed in accordance with a Quality Assurance Program approved by Exelon Nuclear Assessment and accepted by the ANII, with the following additional program requirements:

Completed work shall be certified to be in compliance with this Repair Specification and ASME Section XI, 2001 Edition 2003 Addenda.

C1 Special process procedures shall be provided to the site for acceptance prior to use.

Completed documentation of work shall be submitted to the Repair/Replacement Engineer.

4) Examination P.O. Rev 0 None
5) Testing P.O. Rev 0 Leakaqe Test

ER-AA-330-009 Revision 5 Page 33 of 39

6) Documentation P.O. Rev 0 Vendor to suppv:
1. Certificate of Conformance
2. CMTR for Pivot Shaft - Piece No.7 (to be reviewed by ANIN ASME NIS-2 Form to be completed by Exelon personnel.

ER-AA-330-009 Revision 5 Page 33 of 39 Initial Review.

P.O. Rev g Repair / Replacement Engineer:. Date: /Z , I/.,

ANII Concurrence: Date: 1 P.O. Rev Repair / Replacement Engineer: Date:

ANII Concurrence: Date:

P.O. Rev Repair / Replacement Engineer: Date:

ANII Concurrence: Date:

P.O. Rev Repair / Replacement Engineer: Date:

ANII Concurrence: Date:

P.O. Rev Repair / Replacement Engineer: Date:

ANII Concurrence: Date:

ER-AA-330-009 Revision 5 Page 34 of 39 ATTACHMENT 5 Repair Specification Page 2 of 2

7) Final Acceptance - All documentation shall be accepted by the Repair/Replacement Engineer prior to purchase order closeout.
8) Remarks Vendor 'Trentec" replaced the Pivot Shaft. Hex Head Bolts and Hex Nuts.

Vendor supplied the replacement Parts and oerformed a pressure test to verify leakage, Final Review:

Repair / Replacement Engineer.

ANII Review:

-4 4 ý Date:

Date:

--17,-/

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